ML18018B052

Nine Mile Point Unit 1 - Third Inservice Inspection Interval

ML18018B052
Person / Time
Site:	Nine Mile Point
Issue date:	09/27/1999
From:	Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18018B052 (532)

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VNIAGARA4MOHAWKNiagaraMohawkPowerCorporation300ErieBoulevardWestSyracuse,NewYork13252NineMilePointNuclearPowerStationTHIRDINSERVICEINSPECTIONINTERVALINSERV!CEINSPECTIONPROGRAMPLANPreparedForNineMilePointNuclearPowerStationP.O.Box63Lycoming,NewYork13093CommercialServiceDate:NRCDocketNumber:DocumentNumber:RevisionNumber:0December26,196950-220NMP1-ISI-003Date:September27,1999Preparedby:Approvedby:NMP1SlProgramManager~rlfP'lennR.Perkins-Supervisor,ASMESectionXIProgramsApprovedby:WilliYera/H'1er,EgineeringServicesReviewedby:x-z~HAuorizedNuclearInrviceectorocrr]3sglilt<)()nPICrl8Srrqol'Ib

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElYNIAGARAlIklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TABLEOfCONTENTSTableofContents..RecordofRevision.Abbreviations.GlossaryofTermsAbstractSection1.0introductionSection2.0ASMECodeClass1Systems/Components.Section3.0ASMECodeClass2Systems/Components.Section4.0ASMECodeClass3Systems/Components.CSection5.0ASMECodeClass1,2,and3ComponentSupportsSection6.0AugmentedExaminationsSection7.0RequestsForReliefSection8.0AcceptanceCriteria..Section9.0ASMERepairsandReplacementsSection10.0Records..LISTOfFIGURESI-2i-5i-6i-9.....i-121-1thru1-112-1thru2-163-1thru3-104-1thru4-45-1thru5-6..~.......6-1thru6-357-1thru7-48-1thru8-129-1thru9-9...10-1thru10-14Figure6-3FeedwaterNozzleZones...................................6-19Figure10-1FormNIS-1Owner'sDataReportforlnserviceInspection..........10-6Figure10-2FormNIS-2Owner'sReportforRepairsorReplacements..............10-8Figure10-3OAR-1Owner'sActivityReport.Figure10-4FormNIS-2ARepair/ReplacementPlanCertificationRecord...10-10.10-14File:NMP1PPO.WPD

YNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999LISTOFTABLESTable1-2Table1-6Table2-1Table5-1Table5-2Table6-1Table6-2Table6-3Table6-4NMP1InserviceinspectionPeriodsInspectionProgramBNMP1ValveGroupingsCategoryF-ASelectionProcess.SnubberVisualInspectionFrequencyIGSCCCategoryAWeldSelections.IGSCCCategoryDWeldSelectionsIGSCCCategoryFWeldSelectionsIGSCCCategoryGWeldSelections1-41-10.2-135-45-66-76-8..6-126-12Table6-5IGSCCCategorySWeldSelections.6-13Table6-6Table6-7Table6-8Table6-9IGSCCExaminationRequirementsRoutineInspectionIntetvalsRefuelingCyclesFeedwaterNozzle/SpargerInspectionrecommendations..AugmentedFeedwaterNozzleExamination..6-14......6-17..6-17......6-18Table6-10In-VesselAugmentedExaminations...6-20Table6-11InstrumentNozzles..6-22Table6-12InstrumentNozzles..6-23Table6-13InstrumentNozzles..6-23Table6-14IRMIncoreDryTubeAssemblyTable6-15SIL-455SelectedWeldsTable6-16SIL-474SteamDryerTable6-17RPVHeadCladding....6-24...6-25..6-26..6-27File:NMP1PPO.WPD

VNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999LISTOFTABLES-ContinuedTable6-18UpperCoreGrid.Table6-19SIL-588UpperCoreGridTable6-20SIL-459PumpShafts6-276-28..6-29Table6-21Table6-22CoreSpraySpargerIfB96-03SuctionStrainers.6-29.6-30Table6-23CRDHUpperJWeldandRollAreaListing.6-31Table6-24Table8-1Table8-2Table8-3TeeBasematerial.Class1AcceptanceStandardsClass2AcceptanceStandardsClass3AcceptanceStandards.6-34.8-11.8-11.8-12Table8-4Class1,2,3ComponentSupportsAcceptanceStandards..8-12Table8-5ClassMCAcceptanceStandardsAPPENDICES8-12AppendixAClass1SummaryTablesAppendixBClass2SummaryTablesAppendixCClass3SummaryTables.AppendixDClass1,2and3ComponentSupportSummaryTablesAppendixECodeBoundaryDiagramListingAppendixFReliefRequestsISI-1thruISI-121thru3334thru46.47thru48...49thru58E-1thruE-3F-1thruF-4File:NMP1PPO.WPD

ElVNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REV.No.PROGRAMSECTIONSSection0Section1Section2Section3Section4Section5Section6Section7Section8'ection9RECORDOFREVISIONDATEOFREVISIONAFFECTEDPAGESSeptember27,1999pagei-1thrui-11September27,1999page1-1thru1-11September27,1999page2-1thru2-16September27,1999page3-1thru3-10September27,1999page4-1thru4-4September27,1999page5-1thru5-6September27,1999page6-1thru6-34September27,1999page7-1thru7-4September27,1999page8-1thru8-12September27,1999page9-1thru9-9REASONFORCHANGEInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueInitialIssueSection10September27,1999page10-1thru10-14InitialIssueAppendixA0AppendixBAppendixC0AppendixDSeptember27,1999October26,1999September27,1999October26,1999September27,1999October26,1999September27,1999October26,1999pageA-1thruA-3Table1thru33pageB-1thruB-3Table34thru46pageC-1thruC3Table47thru48pageD-1thruD-3Table49thru58InitialIssueInitialIssueInitialIssueInitialIssueAppendixEAppendixFSeptember27,1999pageF-1thruF-3RR1thruRR12September27,1999pageE-1thruE-3InitialIssueInitialIssueFiie:NMP1PPO.WPD

VNIAGARA4MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ABBREVIATIONSListedbelowaretheabbreviationsutilizedinthisdocument:ANIIANSIASMEB&PVBCBWRBWROGCFRCRCCRDCRACRSCTCTN-SPCRVCUECSDPIFSARFWSFPSGEAuthorizedNuclearInserviceInspectorAmericanNuclearStandardInstituteAmericanSocietyofMechanicalEngineersBoiler&PressureVesselCodeBranchConnectionBoilingWaterReactorBoilingWaterReactorOwner'sGroupCodeofFederalRegulationsCorrosionResistantCladdingContr'olRodDriveSystemCodeRequiredSurfaceAreaCoreSpraySystemCondensateTransferContainmentSpraySystemCodeRequiredVolumeReactorWaterClean-UpSystemEmergencyCoolingSystemDrywellInertingCADandPurgeSystemFinalSafetyAnalysisReportFeedwaterSystemSpentFuelPoolFilteringandCoolingSystemGeneralElectricFile:NMP1PPO.WPD

VN1AGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999GLHPCIIEBIENIHSIISIIVVILPSMSSN/ANBVIABBREVIATIONS(Continued)GenericLetterHighPressureCoolantInjectionSystemInspectionandEnforcementBulletin(USNRC)InspectionandEnforcementNotice(USNRC)InductionHeatStressImprovementInserviceInspectionIn-VesselVisualInspectionsLiquidPoisonSystemMainSteamSystemMagneticParticleExaminationNotApplicableNuclearBoilerVesselInstrumentationNDENMP1NPSNMPCNSSSNWTODPAIDPTRBCLCNondestructiveExaminationNineMilePointNuclearPowerStationUnit1NominalPipeSizeNiagaraMohawkPowerCorporationNuclearSteamSupplySystemNominalWallThicknessOutsideDiameterPipingandInstrumentationDiagramLiquidPenetrantExaminationReactorBuildingClosedLoopCoolingSystemRegulatoryGuide(USNRC)File:NMP1PPO.WPD

hlYNIAGARAH4MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999RHRRHSIRICSILRRRGRPVRWCRXVISDSDCSILSRPSWSSURFSlT.S.TEUFSARUTUSNRCVOLWinISIABBREVIATIONS(Continued)ResidualHeatRemovalSystemResistantHeatStressImprovementRapidInformationCommunicationServicesInformationLetterReactorRecirculationSystemRegulatoryGuide(NRC)ReactorPressureVesselReactorWaterCleanupSystemReactorVesselInstrumentationStructuralDiscontinuityShutdownCoolingWaterSystemServicesInformationLetterStandardReviewPlan(USNRC)ServiceWaterSystemSurfaceExaminationStressImprovementTechnicalSpecificationsTerminalEndUpdatedFinalSafetyAnalysisReportUltrasonicExaminationUnitedStatesNuclearRegulatoryCommissionVolumetricExaminationVisualExamination(suffixnumberdenotestypeofexam,(VT-1,VT-2,VT-3))ComputerizedInserviceInspectionDataBaseManagementSoftwareFile:NMP1PPO.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003LIYNIAGARAH4MOHAWKTHIRDINSERVICEINSPECT(ONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999GLOSSARYOFTERMSASSESS-todeterminebyevaluationofdatacomparedwithpreviouslyobtaineddatasuchasoperatingdataordesignspecifications.AUTHORIZEDINSPECTIONAGENCY-anorganizationthatisempoweredbyanenforcementauthoritytoprovideinspectionpersonnelandservicesasrequiredbySectionXI.AUTHORIZEDNUCLEARINSERVICEINSPECTOR-apersonwhoisemployedandhasbeenqualifiedbyanauthorizedInspectionAgencytoverifythatexaminations,testsandrepairs(thatdonotincludeweldingorbrazing)areperformedinaccordancewiththerulesandrequirementsofSectionXI.AUTHORIZEDNUCLEARINSPECTOR-anemployeeofanauthorizedInspectionAgencywhohasbeenqualifiedinaccordancewithNCA-5000ofSectionIII.COMPONENT-aniteminanuclearpowerplantsuchasavessel,pump,valveorpipingsystem.COMPONENTSUPPORT-ametalsupportdesignedtotransmitloadsfromacomponenttotheload-carryingbuildingorfoundationstructure.Componentsupportsincludepipingsupportsandencompassthosestructuralelementsreliedupontoeithersupporttheweightorprovidestructuralstabilitytocomponents.CONSTANTLOADTYPESUPPORT-springtypesupportthatproducesarelativelyconstantsupportingforcethroughoutaspecifieddeflectionCORESUPPORTSTRUCTURES-thosestructuresorpartsofstructuresthataredesignedtoprovidedirectsupportorrestraintofthecore(fuelandblanketassemblies)withinthereactorpressurevesselCONSTRUCTION-anall-inclusivetermcomprisingmaterials,design,fabrication,examination,testing,inspectionandcertificationrequiredinthemanufacturerandinstallationofitems.CONSTRUCTIONCODE-thebodyoftechnicalrequirementsthatgovernedtheconstructionoftheitem.Defect-aflaw(imperfectionorunintentionaldiscontinuity)ofsuchsize,shape,orientation,location,orpropertiesastoberejectableDISCONTINUITY-alackofcontinuityorcohesion;aninterruptioninthenormalphysicalstructureofmaterialoraproductENFORCEMENTAUTHORITY-aregionalorlocalgoverningbody,suchasaStateorMunicipalityoftheUnitedStatesoraProvinceofCanada,empoweredtoenactandenforceBoilerandPressureVesselCodelegislation.ENGINEERINGEVALUATION-anevaluationofindicationsthatexceedallowableacceptancestandardstodetermineifthemarginsrequiredbytheDesignSpecificationandtheConstructionCodearemaintained.EVALUATION-theprocessofdeterminingthesignificanceofexaminationoroftestresults,includingthecomparisonofexaminationortestresultswithapplicableacceptancecriteriaorpreviousresults.File:NMP1PPO.WPD 0

VNlAGARAUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999GLOSSARYOFTERMS-ContinuedEXAMlNATIONCATEGORY-agroupingofitemstobeexaminedortested.FLAW-animperfectionorunintentionaldiscontinuitythatisdetectablebynondestructiveexaminationHANGER-anitemthatcarriestheweightofcomponentsorpipingfromabovewiththesupportingmembersbeingmainlyintensionIMPERFECTION-aconditionofbeingimperfect;adepartureofaqualitycharacteristicfromitsintendedconditionINDICATION-theresponseorevidencefromtheapplicationofanondestructiveexaminationINSERVICEEXAMINATION-theprocessofvisual,surface,orvolumetricexaminationperformedinaccordancewiththerulesandrequirementsofSectionXI.INSERVICEINSPECTION-methodsandactionsforassuringthestructuralandpressure-retainingintegrityofsafety-relatednuclearpowerplantcomponentsinaccordancewiththerulesofSectionXI.INSPECTION-verificationoftheperformanceofexaminationsandtestsbyanInspector.INSPECTIONPROGRAM-theplanandscheduleforperformingexaminationsortests.SectionXIInserviceInspectionProgramPlan-Atermusedtoaddresstheprogrammaticrequirementsasrequiredby10CFR50.55aandUSNRCGuidelines,dated1981.InserviceInspectionPlanandSchedule-AtermusedtoaddresstheASMESectionXI,AppendixF,InspectionPlan.Long-TermTen-YearInspectionPlan-Atermusedtoaddresstheentiredatabaseprintout(WinISI),thatincludesallitemssubjecttoexamination.InserviceInspectionPeriodPlan-Atermusedtoaddressthoseitemsscheduledforaninspectionperiod(Period1,2or3asapplicable),asrequiredbyInspectionProgram"B".INSPECTOR-anAuthorizedNuclearInserviceInspector,exceptforthoseinstanceswheresodesignatedasAuthorizedNuclearInspector.INSPECTIONINTERVAL-adurationoftime,10-years.INSPECTIONPERIOD-adurationoftimewithinaninspectioninterval,asdeterminedbyPlantTechnicalSpecificationsand/orInspectionProgramBofSectionXl.ITEM-amaterial,part,appurtenance,pipingsub-assembly,componentorcomponentsupport.File:NMP1PPO.WPD

NVNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999GLOSSARYOFTERMS-ContinuedMAINTENANCE-routineservicingorworkundertakentocorrect,adjustorpreventanabnormalorunsatisfactorycondition.NONDESTRUCTIVEEXAMINATION-anexaminationbythevisual,surfaceorvolumetricmethod.OPERATIONALREADINESS-Theabilityofacomponentorsystemtoperformitsintendedfunctionwhenrequired.OPENENDED-aconditionofpipingorlinesthatpermitsfreedischargetoatmosphericorcontainmentatmosphereOWNER-theorganizationlegallyresponsiblefortheoperation,maintenance,safetyandpowergenerationofthenuclearpowerplant.RELEVANTCONDITION-aconditionobservedduringavisualexaminationthatrequiressupplementalexamination,correctivemeasure,repair,replacement,oranalyticalevaluationRECORDABLEINDICATION-anindicationwhichequalsorexceedstherecordingcriteriaREGULATORYAUTHORITY-afederalgovernmentagency,suchastheUnitedStatesNuclearRegulatoryCommission,thatisempoweredtoissueandenforceregulationsaffectingthedesign,construction,andoperationofnuclearpowerplants.SUBSEQUENTPERIOD-isthenextfollowingperiod,evenifitisinthefollowinginterval.SUPPORT-(1)anitemusedtopositioncomponents,resistgravity,resistdynamicloading,ormaintainequilibriumofcomponents;(2)anitemthatcarriestheweightofacomponentorpipingfrombelowwiththesupportingmembersbeingmainlyincompression.STRUCTURALDISCONTINUITY-Asusedinthisprogram:includespipeweldjointstovesselnozzles,valvebodies,pumpcasings,pipefittings(suchastees,elbows,reducers,flanges,etc.conformingtoANSIB16.9)andpipebranchconnectionsandfittings.TERMINALENDS-theextremitiesofpipingrunsthatconnectstructures,components,orpipeanchors,eachofwhichactsasarigidrestraintorprovidesatleast2degreesofrestrainttopipingthermalexpansion.VARIABLESPRINGTYPESUPPORT-aspringtypesupportprovidingavariablesupportingforcethroughoutaspecifieddeflectionVERIFY-todeterminethataparticularactionhasbeenperformedinaccordancewiththerulesandrequirementsofSectionXIeitherbywitnessingtheactionorbyreviewingrecords.Fiie:NMP1PPO.WPD

VNIAGARAVMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ABSTRACTThisdocumentdescribestheUpdatedInserviceInspectionProgramfortheThirdTen-YearInserviceInspectionIntervalfortheNineMilePointNuclearPowerStation,Unit1.Thisdocumentdefinesthebasisforthosepressureretainingcomponentsand/orsystems(includingtheirsupports),whichareclassifiedQualityGroupA,B,andC,(ASMECodeClass1,Class2,andClass3),andsubjecttoexamination,assetforthintheapplicableEditionoftheASMEBoilerandPressureVesselCode,SectionXI,totheextentpracticalwithinthelimitationsofdesign,geometryandmaterialsofconstructionofthecomponentspursuanttoTitle10,Part50,Section.55a(b)(2)oftheCodeofFederalRegulations.TheASMEBoilerandPressureVesselCode,EditionapplicabletotheNineMilePointNuclearPowerStation,Unit1,ThirdInserviceInspectionIntervalProgramPlanandScheduleisthe1989Edition,withnoAddendaofSectionXI,hereafterreferredtoastheCode.File:NMP1PPO.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003HYNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-1of1-11TABLEOFCONTENTSSECTION1-INTRODUCTIONTableofContentsRecordofRevision

1.0INTRODUCTION

1.1InspectionInterval1.2InspectionPeriods1.3ApplicableDocumentsCodeofFederalRegulationsASMECodeEditionsandAddenda..USNRCRegulatoryGuidesNMP1SpecificDocumentsUSNRCNUREGS/SRP'sUSNRCBulletins...............USNRCGenericLettersUSNRCInformationalNotices.....ASMECodeCases.1.4ApplicableCodeEditionsandAddenda1.4.1ThirdInspectionInterval.1.4.2SubsequentCodeEditionandAddenda1.5SystemQualityGroupClassifications1.5.1QualityGroupA1.5.2QualityGroupB1.5.3QualityGroupC1.5.4QualityGroupD1.5.5Application1.5.6OptionalConstruction1.5.7PipingPenetratingContainment.1.5.8ClassificationDiagrams1-31-41-41-41-41-51-51-51-51-61-61-61-61-71-71-71-71-81-81-81-81-81-81-91-91-9File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YN1AGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-2of1-11TABLEOFCONTENTS(Continued)SECTION1-INTRODUCTION1.6InspectionProgramB1.6.1Class1,2and3Components1.6.2ComponentSupports1.7DevelopmentofInspectionProgramPlan1.8SubstituteExaminations1.9Exclusions/Exceptions1.9.1ExaminationCategoryB-J.1.9.2IWEInspectionProgram1.9.3AdditionalPrograms.LISTOFTABLESTABLE1-2NMP1InserviceInspectionPeriodsTABLE1-6InspectionProgramB1-91-91-101-101-111-111-111-41-10File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-3of1-11:,'";;REV!BIO'M,:'.'September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile;NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003NYNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1Qof1-1

11.0INTRODUCTION

ThisdocumentdetailsthebasisandplansfortheInserviceInspectionProgramfortheThirdTen-YearInserviceInspectionIntervalforcomponents,welds,supports,bolting,pumpcasings,valvebodies,andreactorpressurevesselinternalsfortheNineMilePointNuclearPowerStation,Unit1.NiagaraMohawkPowerCorporation(NMPC),istheOwnerofRecord.TheCommercialServiceDatefortheNineMilePointNuclearPowerStation,Unit1isDecember26,1969.1.1InspectionIntervalTheThirdInserviceInspectionIntervalbecomeseffectiveonDecember26,1999andisscheduledtoendonDecember25,2009.1.2InspectionPeriodsTheThirdInserviceInspectionIntervalisdividedintothreesuccessiveinspectionperiodsasdeterminedbycalendaryearsofplantservicewithintheinspectioninterval.IdentifiedbelowaretheperioddatesforthethirdinspectionintervalasdefinedbyInspectionProgramIIBIIInaccordancewithIWB-2412(b)theinspectionperiodspecifiedbelowmaybedecreasedorextendedbyasmuchas1yeartoenableinspectiontocoincidewithNMP1'splantoutages.TABLE1-2NMP1INSERVICEINSPECTIONPERIODSINSPECTIONPERIODSPERIODSTARTDATESPERIODENDDATESREFUELOUTAGEREFUELOUTAGEYEARDecember26,1999December25,2002RFO-162001December25,2002December26,2006RFO-17RFO-1820032005December26,2006December25,2009RFO-192007*TheplantoperatinglicenseiscurrentlyscheduledtoexpireonAugust22,2009.1.3ApplicableDocumentsTheThirdInserviceInspectionProgramforQualityGroupA,B,andC(ASMECodeClass1,2and3),systemsandcomponents(includingtheirsupports)wasdevelopedaftergivingdueconsiderationtothefollowingdocumentsandsubjecttothelimitationsandmodiTicationslistedin10CFR50.55a(b),andtotheextentpracticalwithinthelimitationsofdesign,geometryandmaterialsofconstruction.SpecificareaswithinthisdocumentwherethesedocumentareusedFile:NMPIPP1.WP0

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-5of1-11inthepreparationofthisprogramareaddressedwithintheareaaffected.CodeofFederalRegulations10CFR50.55(a)CodeofFederalRegulations;FederalRegister,Volume64,Number183,datedSeptember22,1999,amendmenttotheregulation.ASMECodeEditionsandAddendaASMEBoilerandPressureVesselCode,SectionsV,1989Edition,"NondestructiveExamination"ASMEBoilerandPressureVesselCode,SectionXI,1989Edition,"RulesforInserviceInspectionofNuclearPowerPlantComponents"ASMEBoilerandPressureVesselCode,SectionXI,1992Editionthroughthe1992Addenda,"RulesforInserviceInspectionofNuclearPowerPlantComponents",SubsectionsIWEandIWL.USNRCRegulatoryGuidesThefollowinglistofRegulatoryGuidesareapplicabletotheNineMilePointNuclearPowerStationThirdInserviceInspectionProgram:1.26QualityGroupClassificationsandStandardsforWater-Steam,andRadioactive-Waste-ContainingComponentsofNuclearPowerPlants,Revision2,June1975.1.65MaterialsandInspectionsforReactorVesselClosureStuds,datedOctober1973,RegulatoryPositionC.4.b.1.84DesignandFabricationCodeCaseAcceptabilityASMESectionIII,Division1,LatestRevision.1.85MaterialCodeCaseAcceptabilityASMESectionIII,Division1,LatestRevision.1.147InserviceInspectionCodeCaseAcceptabilityASMESectionXI,Division1,Revision12..NMP1SpecificDocumentsNineMilePointUnit1UpdatedFinalSafetyAnalysisReport,Sections1,5,7,9,12and16.NineMilePointUnit1TechnicalSpecifications,USNRCDocketnumber50-220,Sections3.6and4.6.File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUni)1NMP1-IS1403LIYNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-6of1-11USNRCNUREGS/SRP'sUSNRCNUREG0313,TechnicalReportonMaterialSelectionandProcessingGuidelinesforBWRCoolantPressureBoundaryPiping,Revision2.USNRCNUREG0619,BWRFeedwaterNozzleandCRDReturnLines.USNRCBulletins82-03StressCorrosionCrackinginThick-Wall,Large-Diameter,StainlessSteel,RecirculationSystemPipingatBWRPlants,Revision1,October28,1982.USNRCGenericLetters88-01USNRCPositiononIGSCCinBWRAusteniticStainlessSteelPiping,January25,1988.88-01NRCPositiononIntergranularStressCorrosionCracking(IGSCC)inBWRAusteniticStainlessSteelPiping,Supplement1,February4,1992.81-11FeedwaterandControlRodDriveNozzleCracking,90-05GuidanceforPerformingTemporaryNon-CodeRepairstoASME(ISI)CodeClass1,2and3PipingandComponents,June15,1990.90-09AlternativeRequirementsforSnubberVisualInspectionIntervalsandCorrectiveActions,December11,1990.94-03IntergranularStressCorrosion(IGSCC)CrackingofCoreShroudinBoilingWaterReactors,July25,1994.98-05BoilingWaterReactorLicenseesUseoftheBWRVIP05ReporttoRequestRelieffromAugmentedExaminationRequirementsonReactorPressureVesselCircumferentialShellWelds,December10,1998.BoilingWaterReactorVesselInspectionProgram(BWRVIP)ReferencesorCommitmentsRequirementsofthecompleteBWRVIPimplementationcriteriafortheThirdTenYearInserviceInspectionIntervaliscurrentlyunderdevelopment.UponcompletionofthisprocesstheapplicableinformationwillbeincorporatedwithinISIProgram.GeneralInformationpertainingtoBWRVIPsimplementationiscontainedintheISIProgramNMP1-ISI-003,Section6.0TitledAugmentedExaminations.USNRCInformationalNotices89-79DegradedCoatingsandCorrosionofSteelContainmentVessels,December1~1989.File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-7of1-11ASMECodeCasesCodeCasesapprovedthroughRegulatoryGuide1.147maybeproposedforrevisiontotheinspectionplan.SpecificCodeCasesusedinthepreparationofthisdocumentareidentifiedbelow.N-416-1AlternativePressureTestRequirementsforWeldedRepairsorInstallationofReplacementItemsbyWelding,Class1,2and3,SectionXI,Division1.RG1.147,Rev.12N-460AlternativeExaminationCoverageforClass1andClass2Welds,SectionXI,Division1.RG1.147,Rev.12N-491-1AlternativeRulesforExaminationofClass1,2,3andMCComponentSupportsofLightWaterCooledPowerPlants,SectionXI,Division1.RG1.147,Rev.12N-509AlternativeRulesfortheSelectionandExaminationofClass1,2and3IntegrallyWeldedAttachments,SectionXI,Division1.RG1.147,Rev.12,Subjecttoconditions.N-524AlternativeExaminationRequirementsforLongitudinalWeldsinClass1and2PipingSectionXI,Division1.RG1.147,Rev.12.N-526AlternativeRequirementsforSuccessiveInspectionofClass1and2Vessels,SectionXI,Division1.SubjecttoRequestforReliefISI-4.N-532AlternativeRequirementstoRepairandReplacementDocumentsRequirementsandInserviceSummaryReportPreparationandSubmissionAsRequiredbyIWA-4000andIWA-5000,SectionXI,Division1.SubjecttoRequestforReliefISI-8.N-573TransferofProcedureQualificationRecordsBetweenOwners,SectionXI,Division1.SubjecttoRequestforReliefISI-10.Note:SeeAppendixD"CodeCases"ofthe10YearInspectionPlanforacompletelistingandcopyofapplicableCodeCases..1.4ApplicableCodeEditionsandAddenda1.4.1ThirdInspectionIntervalPursuanttoTitle10,Part50,Section55a(g)(4),oftheCodeofFederalRegulations,theInserviceInspectionrequirementsapplicabletonondestructiveexaminationandsystempressuretestingfortheThirdInserviceInspectionIntervalarebasedontherulessetforthinthe1989EditionofSectionXI,thatwasendorsedtwelvemonthspriortothestartoftheThirdInspectionInterval.File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-8of-111.4.2SubsequentCodeEditionsandAddendaAspermittedby10CFR50.55a(g)(4)(iv),theNMPCmayelecttomeettherequirementssetforthinsubsequentEditionsandAddendaofSectionXIthatareincorporatedbyreferenceinto10CFR50.55a(b)(2),subjecttotheapplicablelimitationsandmodificationandsubjecttoUSNRCapproval.PortionsofEditionsandAddendamayalsobeusedprovidedthatallrelatedrequirementstotherespectiveEditionsandAddendaaremet.NMPCintendstocontinuallyevaluateandapply,asappropriate,changesinadoptedCodeEditionsandAddendawhichprovidethecontinuingassuranceofthequalityandsafetyofpressureretainingcomponentsandsystems.1.5SystemQualityGroupClassificationsSystemsafetyclassifications,designandfabricationrequirementsmeettheintentof10CFR50.2vandRegulatoryGuide1.26,totheextentpracticalwithinthelimitationsofdesign,geometryandmaterialsofconstructionofthecomponents,asidentifiedwithintheNineMilePointNuclearPowerStation,Unit1,UpdatedFinalSafetyAnalysisReport(UFSAR).Water,steamandradioactivecontainingcomponents(otherthanturbinesandcondensers)aredesignatedQualityGroupA,B,orC,(ASMECodeClass1,2or3),andthataresafety-related.1.5.1QualityGroupA(ASMECodeClass1)QualityGroupAsystemboundariesweredevelopedbasedon10CFR50.2(v),andtheNMP1FSAR,andapplytothereactorcoolantpressureboundarycomponents.TheReactorCoolantsystemincludesasinglecycle,forcedcirculation,GeneralElectricBoilingWaterReactor.1.5.2QualityGroupB(ASMECodeClass2)QualityGroupBsystemboundariesweredevelopedbasedonRegulatoryGuide1.26andtheNMP1FSAR,andapplytothosecomponentsoftheReactorCoolantSystemnotclassifiedasQualityGroupA,(ASMECodeClass1),andthataresafety-related.1.5.3QualityGroupC(ASMECodeClass3)QualityGroupCsystemboundariesweredevelopedbasedonRegulatoryGuide1.26andtheNMP1FSAR,andapplytothosecomponentsthatarenotclassifiedasQualityGroupAorB,(ASMECodeClass1or2),andthataresafety-related.1.5.4QualityGroupD(Non-NuclearSafety-Related)QualityGroupDappliestothosecomponentsnotrelatedtonuclearsafety,andassucharenotincludedwithinthisdocument.Exception,ReactorWaterCleanupSystemweldslocatedoutsidethecontainmentisolationvalves.SeeSection6AugmentedExaminations.File:NMP1PPi.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003NV'IAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-9of1-111.5.5Application1.5.6ApplicationoftherulesofSectionXIaregovernedbythegroupclassificationcriteriaasdefinedabove.TherulesofIWB,IWC,andIWDwereappliedtothosesystemswhosecomponentsareclassifiedQualityGroupA,B,orC,(ASMEClass1,2or3).OptionalConstructionofanComponentOptionalconstructionofacomponentwithinasystemboundarytoaclassificationhigherthantheminimumclassestablishedinthecomponentDesignSpecification(eitherupgradingfromClass2toClass1orfromClass3toClass2)shallnotaffecttheoverallsystemclassificationbywhichtheapplicablerulesofSectionXIaredetermined.1.5.7PipingPenetratingContainmentTheportionsofpipingthatpenetratethecontainmentvesselwhicharerequiredtobeconstructedtoClass1or2rulesforpipingandwhichmaydifferfromtheclassificationofthebalanceofthepipingsystem,neednotaffecttheoverallsystemclassificationthatdeterminestheapplicablerulesofDivision.1.5.8ClassificationDiagramsThesystemQualityGroupA,BandC,(ASMECodeClass1,2and3)classificationinterfacesbetweencomponentsofdifferentqualitygroupsapplicabletoNineMilePointNuclearPowerStation,aredesignatedonvariousASMESectionXIBoundaryDiagrams(P8ID).Thesedesignationsidentifythesystemclassbreaksbycolorcoding.TherulesofIWB,IWCandIWDwereappliedtothesedrawingsinordertodeterminethosecomponents/systemssubjecttoexamination/test.Componentssubjecttosurface,volumetricandvisualexaminationarelistedintheTen-YearInserviceInspectionplantables.AppendixGprovidesalistoftheapplicableASMESectionXIBoundarydiagrams(P8iDiagrams),tothisprogram.CopiesofthesediagramsareavailablethroughtheNMPCdrawingcontrolsystem.1.6InspectionProgramBTheNineMilePointNuclearPowerStationinspectionintervalscomplywithIWA-2432,InspectionProgramB.Withtheexceptionsoftheexaminationsidentifiedin1.6.1,therequiredexaminationsineachexaminationcategoryshallbecompletedinaccordancewithTable1-6.1.6.1Class1,2and3ComponentsTherequiredexaminationsineachExaminationCategoryshallbecompletedduringeachinserviceinspectioninterval,inaccordancewithIWB-2412-1,IWC-2412-1,andIWD-2412-1,withthefollowingexceptions:File:NMP1PP1.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003TNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-10of1-11(1)ExaminationCategoriesB-N-1,B-P,B-Q,C-H,andthesystempressuretestrequirementsofD-A,D-8andD-C;(2)thepercentagerequiredbyNote2ofExaminationCategory8-D;(3)theexaminationsthatmaybedeferredtotheendofaninspectioninterval,asspecifiedinTableIW8-2500-1.(4)IftherearelessthanthreeitemstobeexaminedinanExaminationCategory,theitemsmaybeexaminedinanytwoperiods,orinanyoneperiodifthereisonlyoneitem,inlieuofthepercentagerequirementsofTable1-6below.(5)WithinvariousCodeCategoriesthetotalnumberofitemsscheduledforexaminationexceedsInspectionProgram"8"requirements.AdjustmentstothoseCodeCategorieswhichexceedtheallowableProgram"8"percentages,maybereducedtomeetProgram"8"requirements.1.6.2ComponentSupportsTherequiredexaminationsshallbecompletedinaccordancewiththeinspectionscheduleestablishedforthecomponentsunderIWB,IWC,andIWD.TABL'E1-6INSPECTIONPROGRAM:BInspectionIntervalNMP13'6.InserviceInspectionIntervalInspectionPeriodCalendarYearsofPlantServiceWithintheInterval10MinimumExaminationCompleted,%16%50%1PPMaximumExaminationCredited,%Note.1234%67%100%Note:1ExcetasnotedinTableIW8-2500-1,81.30.Note:(1)Theexaminationofshell<oAangeweldsmaybeperformedduringthefirstandthirdinspectionperiodsinconjunctionwiththenozzleexaminationsofexaminationcategoryB-D.Atleast50%ofshell-to-flangewelds,shallbeexaminedbytheendoftheFirstInspectionPeriod,andtheremainderbytheendoftheThirdInspectionInterval.(2)Atkit25%butnotmorethan50%(credited)ofthenozzlesshallbeexaminedbytheendofthefirstinspectionperiod,andtheremainderbytheendofthelastinspectionperiod,oftherespectiveinspectioninterval.(Seeparagraph1.6.1(2)).1.7DevelopmentofInspectionProgramPlanSections2through6detailthenarrativedescriptionoftheNineMilePointUnit1ThirdlnsefviceInspectionProgramPlanbasisforQualityGroupA,8orC,(ASMECodeClass1,File:NMPIPPI.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANRev.0Date:September27,1999Pae1-1of1-112and3),(includingtheirSupportsandAugmentedExaminations),ofcomponentsand/orsystemssubjecttoexamination/test.1.8SubstituteExaminationsNMPCmaysubstituteitemsscheduledintheInspectionPlanforothersnotpreviouslyscheduledwhentheoriginalselectionwaspartoftheadditionalpipingwelds.Thissubstitutionmaybedoneduetosuchconditionsaslimitedphysicalaccess,highradiationlevels,etc.SuchchangeswillbenotedintheSummaryReportsubmittalasrequiredbyIWA-6000oftheapplicableCodeEdition.Specificexaminationsthatarerequired,andcannotbecompletedwithintheperiod/intervalwillbeidentifiedwithintheSummaryReport,andasapplicable,maybethesubjectofarequestforrelief.1.9Exclusions/ExceptionsThisparagraphdefinestheexclusions/exceptions,NMPChastakenduetotheunitbeingDocketedpriortoJune1978.1.9.1ExaminationCategoryB-JAllterminalendsandjointsineachpipeorbranchrunconnectedtoothercomponentswherethestresslevelsexceedeitherofthefollowinglimitsunderloadsassociatedwithspecificseismiceventsandoperationalconditions:(1)Primaryplussecondarystressintensityrangeof2.4Smforferriticandstainlesssteel(2)cumulativeusagefactorUof0.41.9.2IWEInspectionProgramTheInserviceInspectionProgramforClassMC,SubsectionIWEandIWLisnotaddressedwithinthisprogram,withtheexceptionsofRepairsandReplacementsasdefinedinSection9.1.9.3AdditionalProgramsInadditiontotheaboveitems,thefollowingProgramsareoutsidethescopeofthisdocument.Theyareaddressedinseparatedocuments.SnubberExaminationandTestingProgramRepairandReplacementProgramInservicePumpandValveTestProgramMetalContainmentExaminationProgramSystemPressureTestProgramContainmentPressureTestProgramFile:NMP1PP1.WPD

NVNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999P2-1f2-16TableofContentsRecordofRevisionTABLEOFCONTENTSSECTION2-CLASS1SYSTEMS2-12-22.0CLASS1SYSTEMS/COMPONENTS2.1ASMECodeExemptions2.2Component/PipingExaminationDevelopment2.2.1CategoryB-A2.2.2CategoryB-B2.2.3CategoryB-D2.2.4CategoryB-E2.2.5CategoryB-F2.2.6CategoryB-G-12.2.7CategoryB-G-22.2.8CategoryB-H2.2.9CategoryB-J2.2.10CategoryB-K-12.2.11CategoryB-L-1andB-L-22.2.12CategoryB-M-1andB-M-22.2.13CategoryB-N-1,B-N-2,andB-N-3.2.2.14CategoryB-02.2.15CategoryB-P2.2.16CategoryB-Q2.2.17SuccessiveInspections.2-32-32-32-32-52-52-62-62-72-92-92-102-112-122-122-152-162-162-162-16File:NMP1PP2.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003hlVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-;-'.-.*RBCORDOF.REVISIONREVISION'.'No."0"DATE;,;.".:,,September27,1999'-'.-;;"AFF,ECTED'~'",~PAGES':'ntireDocumentREASON;FORREVISION',UpdatedInserviceInspectionProgramPlanforthe3"'enYearInserviceInspectionInterval0File:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003LIYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVAIRey.PINSERVICEINSPECTIONPROGRAMPLANDate:September27,19992.0CLASS1SYSTEMS/COMPONENTSTheASMECodeClass1systemboundariessubjecttoexaminationandtestingweredevelopedbasedupontherequirementsof10CFR50.2(v)andNineMilePointUnit1(NMP1),FinalSafetyAnalysisReport(FSAR).TheASMECodeClass1componentsandsystems(includingtheirsupports)subjecttoexaminationandtestingaredescribedindetailbelow:2.1ASMECodeExemptionsIWB-1220-Thefollowingcomponents(orpartsofcomponents)areexemptedfromthevolumetricandsurfaceexaminationrequirementsofIWB-2500:(a)ComponentsthatareconnectedtotheReactorCoolantSystemandpartofthereactorcoolantpressureboundaryandthatareofsuchasizeandshapesothatuponpostulatedrupturetheresultingflowofcoolantfromtheReactorCoolantSystem,undernormalplantoperatingconditions,iswithinthecapacityofmakeupsystemswhichareoperablefromon-siteemergencypower.(b)1.Pipingof1"nominalpipesizeandsmaller;and2.Componentsandtheirconnectionsinpipingof1"nominalpipesizeandsmaller.(c)Reactorvesselheadconnectionsandassociatedpiping,2"nominalpipesizeandsmaller,madeinaccessiblebycontrolroddrivepenetrations.2.2Component/PipingExaminationDevelopmentAnarrativediscussionofClass1componentssubjecttoexaminationandtestingaredescribedindetailbelow:2.2.1CategoryB-A,PressureRetainingWeldsinReactorVesselAllexaminationsareperformedfromtheinsideand/oroutsidesurfaceusingmanual/automatedinspectionequipment,(asapplicable)andvolumetricexaminationtechniques.NoeNMPCsubmittedandreceivedauthorizationtoutilizean"AlternativeforExaminationofReactorPressureVesselShellWelds,(TACNo.MA4383).AsauthorizedbytheUSNRCtheuseofPDIqualifiedpersonnelandproceduresresultsinamoresensitiveexaminationandwillprovideaddedassuranceforflawdetectionandsizing,andisanacceptablealternativetotherequirementsofthe1989EditionofSectionXICodeandRegulatoryGuide1.150.TheerrorbandforflawsizinghasbeenestablishedwithinthelimitsofASMESectionXI,AppendixVIII.File:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElVNIAGARAl1UMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999BB2-eScopeofExamination-includesvolumetricexaminationofessentially100%ofalllongitudinalandcircumferentialshellweldlengths.(doesnotincludeshelltoflangeweld).PursuanttoUSNRCGenericLetter98-05andBWRVIP-05,NMPCappliedforandwasgrantedrelieffromperformingexaminationsofthecircumferentialweldtilltheendoftheNMP1operatinglicense.(August22,2009)(4)B1.11Circumferentialshellwelds,nonerequired(12)B1.12Longitudinalshellwelds,(12)requiredSubjecttoRequestforRelief:ISI-1GrantedunderUSNRCTACNo.MA4768,andISI-4.B121BScopeofExamination-includesvolumetricexaminationofessentially100%ofaccessiblelengthofallcircumferentialandmeridionalheadwelds.(2)B1.21Circumferentialheadweids,(2)required(14)B1.22Meridionalheadwelds,(14)requiredBBScopeofExamination-includesvolumetricexaminationofessentially100%ofaccessiblelengthofallcircumferentialandmeridionalheadwelds.(1)B1.21Circumferentialheadwelds,(1)required(8)B1.22Meridionalheadwelds,(8)requiredSubjecttoRequestforRelief:ISI-2BScopeofExamination-Volumetricexaminationof100%oftheshelltoflangeweld.Haia2:(1)B1.30Circumferentialshelltoflangeweld,(1)requiredSubjecttoRequestforRelief:ISI-2andISIS.Ifpartialexaminationsareconductedfromtheflangeface,theremainingvolumetricexaminationsrequiredtobeconductedfromthevesselwallmaybeperformedatorneartheendofeachinspectioninterval.TheexaminationmaybeperformedduringthefirstandthirdinspectionperiodsinconjunctionwiththenozzleexaminationsofExaminationCategoryB-D(ProgramB).Atleast50%oftheweldshallbeexaminedbytheendoftheFirstInspectionFile:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElVNlAGARAH4MOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-Period,andtheremainderbytheendoftheThirdInspectionPeriod.BScopeofExamination-includesvolumetricandsurfaceexaminationofessentially100%ofthereactorvesselheadtoflangeweldlength.(1)B1.40Circumferentialheadtoflangeweld,(1)required,1/3EachPeriodSubjecttoRequestforRelief:ISI-2NotapplicabletoNineMilePointNuclearPowerStation2.2.2CategoryB-B,PressureRetainingweldsinvesselsotherthanReactorVessels.ThisExaminationCategoryisnotapplicabletoNineMilePointNuclearPowerStation.2.2.3CategoryB-D,FullPenetrationWeldsofNozzleinVessels(ProgramB)ScopeofExamination-Volumetricexaminationof100%ofallnozzleswithfullpenetrationweldstovesselshell(orhead)andintegrallycastnozzles.(40)B3.90RPVNozzleWelds,(40)required(40)B3.100RPVNozzleInnerRadius,(40)requiredSubjecttoRequestforRelief:ISI-3Atleast25%butnotmorethan50%(credited)ofthenozzlesshallbeexaminedbytheendoftheFirstInspectionPeriod,andtheremainderbytheendoftheinspectioninterval.AugmentedExaminationsoftheFeedwaterNozzle,inaccordancewithUSNRCNUREG0619,GenericLetter81-11,ILEBulletin80-13,revision1,Supplement1andGE-NE523-A71-0594areaddressedinSection6,AugmentedExaminations.WerepracticalCodecreditwillbetakenduringtheseAugmentedexamination.PrBNotapplicabletoNineMilePointNuclearPowerStation.File:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNIAGARAklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.QINSERVICEINSPECTIONPROGRAMPLANDate:September27,1999NotapplicabletoNineMilePointNuclearPowerStation.NotapplicabletoNineMilePointNuclearPowerStation.2.2.4CategoryB-E,PressureRetainingPartialPenetrationWeldsinVesselsB-VvNNoScopeofExamination-VisualVT-2examinationon25%ofallpartialpenetrationweldseachinterval.TheexaminationsareperformedduringtheSystemPressureTesting.TheseexaminationsandtestsareaddressedintheNineMilePointUnit1InservicePressureTestProgram,DocumentNMP1-PT-003..(0)B4.11Vesselnozzles,notapplicabletoNMP1(129)B4.12Controlroddrivenozzles,(32)required(64)B4.13Instrumentationnozzles,(16)required2.2.5CategoryB-F,PressureRetainingDissimilarMetalWeldsScopeofExamination-VolumetricandsurfaceorsurfaceexaminationsarerequiredofalldissimilarmetalsafeendweldsineachloopandconnectingbranchoftheReactorCoolantSystem.Forthereactorvesselnozzledissimilarmetalsafeendwelds,theexaminationmaybeperformedcoincidentwiththevesselnozzleexaminationsrequiredbyExaminationCategoryB-D.ExaminationCategoryB-FweldsarescheduledandexaminedaspartoftheIGSCCAugmentedInspectionProgram.TheextentandfrequencyoftheexaminationsareinaccordancewithNUREG0313,Revision2andGenericLetterGL88-01,Supplement1.SeeSection6.0ofthisProgramfordetails.CompletedexaminationsshallbeusedtosatisfythepercentagerequirementsofInspectionProgram"B"andNUREG0313,asapplicable.(33)B5.10NPS4"orLargerNozzle-to-Safeendbuttwelds,(33)req'd(4)B5.20LessthanNPS4"Nozzle-to-Safeendbuttwelds,(4)req'd(N/A)B5.30Nozzle-to-Safeendsocketwelds,NotapplicabletoNMP1AugmentedexaminationrequirementsofNUREG-0313,Rev.2,NRCGenericLetter88-01,Sup.1,BWRVIP-06,27,and49,SIL455,Rev.1,Sup.1,SIL571,andRICSIL072arediscussedinSection6ofthisdocument.File:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElVNlAGARAH4MOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.QINSERVICEINSPECTIONPROGRAMPLANDate:September27,1999z8NotapplicabletoNineMilePointNuclearPowerStation.o0NotapplicabletoNineMilePointNuclearPowerStation.82NotapplicabletoNineMilePointNuclearPowerStation.-D4IIScopeofExamination-VolumetricandsurfaceorsurfaceexaminationsarerequiredofalldissimilarmetalsafeendweldsineachloopandconnectingbranchoftheReactorCoolantSystem.ExaminationCategoryB-FweldsarescheduledandexaminedaspartoftheIGSCCAugmentedInspectionProgram.Theextentandfrequencyofexaminations'reinaccordancewithNUREG0313,Revision2andGenericLetterGL88-01,Supplement1.SeeSection6.0ofthisProgramfordetails.CompletedexaminationsshallbeusedtosatisfybothInspectionProgram"B"andNUREG0313requirements.(N/A)85.130~4"NPSdissimilarbuttwelds,NotapplicabletoNMP1(N/A)85.140<4"NPSdissimilarbuttwelds,NotapplicabletoNMP1(N/A)85.150dissimilarsocketwelds,NotapplicabletoNMP12.2.6Category8-G PressureRetainingBolting,GreaterThan2in.InDiameterea88.4ScopeofExamination-Examinationincludesallbolts,studs,nuts,bushings,andthreadsinflangestudholes.Boltingmaybeexaminedinplaceundertension,whentheconnectionisdisassembled,orwhentheboltingisremoved.Forheatexchangers,piping,pumps,andvalves,examinationsarelimitedtocomponentsselectedforexaminationunderExaminationCategoriesB-B,B-J,B-L-2,andB-M-2.Examinationsconsistofvisualexamsofreactorvesselclosureheadnuts,volumetricexamsofRPVstudsinplace,andsurfaceexamsofRPVstudswhenremoved.RegulatoryGuide1.65,regulatorypositionC.4.bwillbeinvokedbyNMPCtoexaminearepresentativesampleofaminimumof(12)studsonageometricdistributionof(3)studswithineach90degreesegment.Avolumetricexaminationofthethreadsinthebasematerialofthereactorvesselflangewillbeconductedonlywhentheconnectionsaredisassembled.AVisual(VT-1)File:NMP1PP2.WPD

ElYNIAGARAHllMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999Pe2-of2-1examinationoftheRVwashersandbushingsmaybeexaminedinplace,whentheconnectionisdisassembledorwhentheboltingisremoved.Flangesurfaces,whentheconnectionisdisassembled,include1inchannularsurfaceofflangesurroundingeachstud.(64)B6.10Nuts,(64)required,1/3eachperiod(64)B6.20StudsinPlace,(64)required,1/3eachperiod(64)B6.30Studs,whenremoved,(12)min.required,(4)eachperiod(64)B6.40ThreadsinLigaments,(64)required,1/3eachperiod(128)B6.50Washers,(128)required,1/3eachperiod(64)B6.50Bushings,(64)required,1/3eachperiodSubjecttoRequestforRelief:ISI-11PrB70B6NotapplicabletoNineMilePointNuclearPowerStation.B690B61BNotapplicabletoNineMilePointNuclearPowerStation.mB612B3BNotapplicabletoNineMilePointNuclearPowerStation.piIB16BNotapplicabletoNineMilePointNuclearPowerStation.BB6200ScopeofExamination-Allbolts,studs,nuts,bushings,andflangesurfaces.Examinationsapplicabletofive(5)ReactorRecirculationPumps32-185,32-186,32-187,32-188and32-189.~No5.PumpboltingislimitedtothepumpselectedunderExaminationCategoryB-L-2.Boltingmaybeexaminedinplaceundertension,whentheconnectionisdisassembled,orwhentheboltingisremoved.Bushingsandthreadsinbasematerialofflangesarerequiredtobeexaminedonlywhentheconnectionsaredisassembled.Bushingsmaybeexaminedinplace.Flangesurfacerequires1inchannularsurfaceofflangesurroundingeachstudhole.(80)B6.180Studs,16studsperpump,(16)onepumprequired(5)B6.190Flangesurfaces,(1)perpump,onepumprequired(240)B6.200Nuts,Bushings,andWashers,(48)perpump,onepumpFile:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003hlVNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.PINSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-requiredScopeofExamination-Allbolts,studs,nuts,bushings,andflangesurfaces.ExaminationsapplicabletoFeedwater,CoreSprayandShutdownCoolingsystemsandarelimitedtovalveselectedunderCategoryB-M-2.(5)B6.210ValveBolts,(3)required(5)B6.220ValveFlanges,(3)required(9)B6.230ValveNuts,Bushings,washers,(5)required2.2.7CategoryB-G-2,PressureRetainingBolting,2in.AndLessinDiameterBBB7BScopeofExamination-VisualVT-1examinationeachintervalofallbolts,studs,andnuts.ExaminationsarelimitedtocomponentsselectedforexaminationunderExaminationCategoryB-B,B-J,B-L-2,andB-M-2.(18)B7.10ReactorPressureVessel,(18)required(N/A)B7.20Pressurizer,NotapplicabletoNMP1.(N/A)B7.30SteamGenerator,NotapplicabletoNMP1.(N/A)B7.40HeatExchanger,NotapplicabletoNMP1.(12)B7.50PipingFlangeBolting,(12)required(80)B7.60Pump,(5)pumps16capscrewsperpump,onepumprequired(75)B7.70Valves,(33)required(129)B7.80CRDHousing,whendisassembledHaia%.AugmentedexaminationrequirementsofSIL419andSIL483Revision2arediscussedinSection6ofthisprogram.2.2.8CategoryB-H,IntegralAttachmentsforVesselsScopeofExamination-Examinationincludesessentially100%ofthelengthoftheattachmentweldateachattachmentsubjecttoexamination.ExaminationslimitedtotheReactorPressureVesselskirtweldandstabilizers.ExaminationswillbeperformedinaccordancewiththealternaterequirementsofCodeCaseN-509,"AlternativeRulesfortheSelectionandExaminationofClass1,2and3IntegrallyWeldedAttachmentsSectionXI,Division1".CodeExaminationCategoriesandItemNumbersareasdenotedintheCodeCase.SeeExaminationCategoryB-KFile:NMP1PP2.WPD

NineMllePointNuclearPowerStationUnit1NMP1-Isl-003TNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.QINSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-BNotapplicabletoNineMilePointNuclearPowerStation.BNotapplicabletoNineMilePointNuclearPowerStation.BNotapplicabletoNineMilePointNuclearPowerStation.2.2.9CategoryB-J,PressureRetainingWeldsinPipingBBBScopeofExamination-Alldissimilarmetalpipewelds,terminalends,plusanadditionalnumberofpipingweldssothat25%ofallnon-exemptcircumferentialandbranchconnectionpipeweldsareexamined.HaIIJITableIWB-2500-1,ExaminationCategolyB-J,Footnote(1)(b)(1)and(2)arenotapplicabletoNMP1,withtheexceptionoftheReactorRecirculationsystem,duetotheunitbeingdocketedpriortoJune1978.AllaugmentedMainSteamandFeedwaterSystemwelds,totheextentpracticalshallbeusedtosatisfythepercentagerequirementsofInspectionProgram"B"andtheaugmentedrequirementsofNUREG0313,GenericLetter88-01,Supplement1,I8EBulletin80-13,SIL289andINPOSER5-85shallalsobeusedforsatisfyingthepercentagerequirementsofInspectionProgram"8",totheextentpractical.SeeSection6.0AugmentedExaminationsofthisProgramfordetails.Alllongitudinalpipeweldsintersectinganyoftheselectedcircumferentialweldswillalsobeexamined.AsanalternatetoTableIWB-2500-1,ASMECodeCaseN-524,"AlternativeExaminationRequirementsforLongitudinalWeldsinClass1PipingSectionXI,Division1",shallbeusedasdefinedbelow:(A)Whenonlyasurfaceexaminationisrequired,examinationoflongitudinalpipingweldsisnotrequiredbeyondthoseportionsoftheweldswithintheexaminationboundariesofintersectingcircumferentialwelds.(B)Whenbothsurfaceandvolumetricexaminationsarerequired,examinationoflongitudinalpipingweldsisnotrequiredbeyondthoseportionsoftheweldswithintheexaminationboundariesofintersectingcircumferentialweldsprovidingthefollowingrequirementsaremet.(1)Wherelongitudinalweldsarespecifiedandlocationsareknown,examinationrequirementsshallbemetforbothtransverseandparallelflawsattheintersectionoftheweldsandforthatlengthofFile:NMP1PP2.WPD e

VNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19992-1f2-1longitudinalweldwithinthecircumferentialweldexaminationvolume;(2)Wherelongitudinalweldsarespecifiedbutlocationsareunknown,ortheexistenceoflongitudinalweldsisuncertain,theexaminationrequirementsshallbemetforbothtransverseandparallelflawswithintheentireexaminationvolumeofintersectingcircumferentialwelds.(345)B9.11Circumferentialwelds,(86)required(288)B9.12Longitudinalwelds,Nominimumrequired(164)B9.21Circumferentialwelds,(41)required(None)B9.22Longitudinalwelds,NotapplicabletoNMP1(9)B9.31BranchConn.NPS4"orLarger,(2)required(26)B9.32BranchConn.LessthanNPS4",(7)required(69)B9.40Socketwelds,(17)required(613)NonexemptWeldssubjecttoexamination,(153)required,(154)scheduled(288)Long.Weldssubjecttoexamination,(46)selectedSeeAppendixATablesforselectiondetails.2.2.10CategoryB-K,IntegralAttachmentstoPiping,Pumps8Valves'BB12BumVachmenScopeofExamination-VolumetricorSurfaceexaminationtoincludeessentially100%ofthelengthoftheattachmentweldateachintegrallyweldedattachmentsubjecttoexamination.Integralattachmentsselectedforexaminationwillconsistofattachmentswhosebasematerialdesignthicknessisequalto5/8inchandgreater.TheexaminationsincludeonlytheweldedattachmentstopipingrequiredtobeexaminedunderExaminationCategoryB-Jandtheweldedattachmentstopumpsandvalveintegraltosuchpiping.ExamirlationswillbeperformedinaccordancewiththealternaterequirementsofCodeCaseN-509,"AlternativeRulesfortheSelectionandExaminationofClass1,2and3IntegrallyWeldedAttachmentsSectionXI,Division1".ExaminationCategoryandItemNumbersshallbeasdefinedwithintheCodeCase.~NoeInadditiontothoseconditionsspecifiedintheCodeCase,aminimum10%sampleofintegrallyweldedattachmentsforeachitemineachCodeClassperintervalwillbeexamined.(6)B10.10VesselIntegralAttachments,(1)required(155)B10.20PipingIntegralAttachments,(16)required(0)B10.30PumpIntegralAttachments,NotapplicabletoNMP1(8)B10.40ValveIntegralAttachments,(1)requiredFiie:NMP1PP2.WPD

hlYNIAGARAIl4MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19992-2f2-1SubjecttoRequestforRelief:ISI-52.2.11CategoryB-L-1,PressureRetainingWeldsinPumpCasings,B-L-2,PumpCasings'B$ScopeofExamination-100%volumetricexaminationofallweldsinonePump.ThepumpselectedshallbebasedonpumpdisassemblyformaintenanceunderB-L-2orendofinspectioninterval,whichevercomesfirst.NotapplicabletoNineMilePointNuclearPowerStationUnit1.Thefive(5)ReactorRecirculationPumpsdonothavecasingwelds.BScopeofExamination-Visualexaminationoftheinteriorsurfacesofoneofthefive(5)ReactorRecirculationPumpswhendisassembledformaintenance.Pumptobeidentifiedwhenpumpisdisassembled.(5)B12.20Recirc.Pumps(1)PumpRequired2.2.12CategoryB-M-1,PressureRetainingWeldsinValveBodies,B-M-2,ValveBodies2ValvBNotapplicabletoNineMilePointNuclearPowerStationUnit1.ValveslessthanNPS4donothaveanyvalvebodywelds.B24VvBoP"oLaScopeofExamination-Volumetricexaminationtoincludeessentially100%ofweldlength.Examinationsarelimitedtoatleastonevalvewithineachgroupofvalvesthatarethesamesize,constructionaldesign,andmanufacturingmethod,andperformsimilarfunctionsinthesystem.(6)ValveBodyWelds,(1)required8VvBodIScopeofExamination-VisualVT-3examinationofatleastonevalveinagroupofvalvesthatarethesamesize,constructionaldesign(suchasglobe,gate,orcheckvalves),andmanufacturingmethod,andthatperformsimilarfunctionsinthesystem(suchascontainmentisolationandsystemoverpressureprotection).Examinationsareperformedonceperintervalwhendisassembledformaintenanceorrepair.Valvestobeidentifiedwhenvalveisdisassembled.File:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-Isl-003ElVNIAGARAHLlMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-TheTablebelowlistallvalvesgroupedbysystem,size,andtypesubjecttoexaminationunderB-M-2.GRP'O..SYS"SIZE',TYPE.G"f"'D,:"?;.:,VALVE.Tabie:,2-1"'...VALVE;GROUPINGS.~'-M-2"'-M-1""';;;","',",;""',SELECTV01V02V0301.024.0'LOBEN/A01.06.0'ATEN/A01.06.0'eliefN/A01-01-VB01-02-VB01-03-VB01-04-VB01-07-VB01-08-VB01-09-VB01-10-VB01-11-VB01-12-VB01-102-A-SV801-102-B-SVBOt-102-C-SVB01-102-D-SVB01-102-E-SVB01-102-F-SVB01-01-VBY01-02-VBY01-03-VBY01-04-VBY01-07-VBY01-08-VBY01-09-VBY01-10-VBY01-11-VBY01-12-VBY01-102-A-SVBY01-102-B-SVBY01-102-C-SVBY01-102-D-SVBY01-102-E-SVBY01-102-F-SVBYN/AN/A01-102-A-WD-00101-102-B-WD-00101-102-C-WD-00101-102-D-WD-00101-102-E-WD-00101-102-F-WD-0011Valveamongagroupofvalves1Valveamongagroupofvalves1ValveamongagroupofvalvesV04VOSV06V0731.018.0'heck31.018.0'ate32.028.0'ate33.06.0'ate31-01R-VB31-02R-VBN/AN/A31-07-VB31-08-VB32-380-VB32-381-VB32-382-VB32-383-VB32484-VB32-375-VB32-376-VB32-377-VB32-378-VB32479-VB33-01R-VB33-02R-VB31-01R-VBY31-02R-VBY31-07-VBY31-08-VBY32480-VBY32.381-VBY32482-VBY32-383-VBY32-384-VBY32-375-VBY32476-VBY32-377-VBY32-378-VBY32-379-VBY33-01R-VBY33-02R-VBYN/AN/A1Valveamongagroupofvatvfts1Valveamongagroupofvalves1Valveamongagroupofvalves1ValveamongagroupofvalvesV0838.014.0GateN/A38-01-VB38-02-VB38-13-VB38-01-VBY38-02-VBY38-13-VBY1ValveamongagroupofvalvesFile:NMP1PP2.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003NVNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.PINSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-GRP'O.SYS'.""SlZElD:,'"',Tabfe2-1VALVErGROUPINGSTYPE'BG '-';,'8 2VALVE'.SELECTV0939.010.0'lobeN/A39-05-VB39-06-VB39-05-VBY39-06-VBYN/A1ValveamongagroupofvalvesV1038.014.0'heck38-12-VBN/A38-12-VBY1ValveamongagroupofvalvesV1140.012.0'heck40-03-VB40-13-VBN/A40.03-VBY40-13-VBY1ValveamongagroupofvalvesV12V13V1439.010.0'3.06.0'0.012.0'heckN/ACheckN/AGate39-03-VB39-04-VB33-03-VB33-04-VB40-01-VB40-02-VB40-09-VB40-10-VB40-11-VB40-12-VB39-03-VBY39-04-VBY33.03-VBY33.04-VBY40-01-VBY40-02-VBY40-09-VBY40-10-VBY40-11-VBY40-12-VBYN/AN/AN/A1Valveamongagroupofvalves1Valveamongagroupofvalves1ValveamongagroupofvalvesV15V16V1739.010.0'0.06.0'0.06.0'ateGateSafetyReliefN/AN/AN/A39-01R-VB39.02R-VB40-05-VB40-06-VBCH-576-12A-BCH-576-12B-BCH-576-12C-BCH.576-12D-BCH-576-12F-BCH.576-12G-BCH-576-12H.BCH-576-12J-B39-01R-VBY39-02R-VBY40-05-VBY40-06-VBYV-BK-01-119AV-BK-01-119BV-BK-01-119CV-BK-01-119DV-BK-01-119FV.BK-01-119GV-BK-01-119HV-BK-01-119JN/AN/A1Valveamongagroupofvalves1Valveamongagroupofvalves1ValveamongagroupofvalvesFile:NMP1PP2.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.QINSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-GRPNa.BYSStZETYPE'B-G1lo...',',"'VALVE,,'i'Table'i2>>I.':.i'i'I.IVALVE.GROUPINGSB-'6-2.'B.M.1:"SELECTV1839.010.0'ateN/A39-07R-VB39-08R-VB39-09R-VB39-10R-VB39-07R-VBY39-08R-VBY39-09R-VBY39-10R-VBY1Valveamongagroupofvalves2.2.13CategoryB-N-1,InteriorofReactorVessel,B-N-2,IntegrallyWeldedCoreSupportStructuresandInteriorattachmentstoReactorVessels,B-N-3,RemovableCoreSupportStructures.AugmentedIVVIexaminationsareaddressedinSection6ofthisProgram.0ScopeofExamination-VisualVT-3examinationofaccessibleareas(areasaboveandbelowthereactorcoremadeaccessibleforexaminationbyremovalofcomponentsduringnormalrefueling),onceeachinspectionperiod.(3)AccessibleAreas,onceeachperiod'B0ReactorVessel(BWR)ScopeofExamination-VisualVT-1examinationofaccessibleweldsofinteriorattachmentswithintheBeltlineregion(onceperinterval).(5)InteriorAttachments,(5)requiredceScopeofExamination-VisualVT-3examinationofaccessibleweldsofinteriorattachmentsbeyondtheBeltlineregion(onceperinterval).(N/A)InteriorAttachments,NotapplicabletoNMP10cuScopeofExamination-VisualVT-3examinationofaccessiblesurfacesofcoresupportstructures(onceperinterval).(49)Accessiblesurfaces,(49)requiredB37IFilo:NMP1PP2.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003ElVNIAGARAH4MOHAWKTHIRDINSERVICEINSPECTIONINTERVALRey.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19992-ReactorVessel(PWR)NotapplicabletoNineMilePointNuclearPowerStationUnit1.AugmentedexaminationrequirementsareaddressedinSection6ofthisProgram.2.2.14CategoryB-O,PressureRetainingWeldslnControlRodHousings'BWDScopeofExamination-Volumetricorsurfaceexaminationof10%oftheperipheralCRDhousings.(129)CRDHousings,(32)PeripheralCRDHousings,(3)required(10%)SubjecttoRequestforRelief:ISI-62.2.15CategoryB-P,AllPressureRetainingComponentsScopeofExamination-SystempressuretestsareconductedonAllClass1systemsandcomponentsinaccordancewiththeNineMilePointUnit1SystemPressureTestingProgram,DocumentNMP1-PT-003.2.2.16CategoryB-Q,SteamGeneratorTubingNotapplicabletoNineMilePointNuclearPowerStationUnit1.2.2.17SuccessiveInspectionsThesequenceofcomponentexaminationsestablishedduringthefirstinspectionintervalwasrepeatedduringthethirdinspectionintelval,totheextentpractical.InaccordancewithIWB-2420(b),severalweldsexaminedduringthesecondinspectionintervalwereevaluatedinaccordancewithIWB-3142.4,andweredeterminedbyanalysistoqualifyasacceptableforcontinuedservice.Theareascontainingtheseindicationsshallrequirereexaminationduringthethirdinspectioninterval.ApplicableweldsareuniquelyidentifiedwithintheinserviceinspectionplanTables.File:NMP1PP2.WPD

HVNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTSSECTION3-CLASS2SYSTEMSTableofContents..RecordofRevision3.0CLASS2SYSTEMS/COMPONENTS..3.1ASMECodeExemptions3.1.1IWC-12213.1.2IWC-12223.1.3IWC-1230.3.2Component/PipingExaminationDevelopment3.2.1CategoryC-A3.2.2CategoryC-B3.2.3CategoryC-C3.2.4CategoryC-D3.2.5CategoryC-F-13.2.6CategoryC-F-23.2.7CategoryC-6..3.2.8CategoryC-H..3.3SuccessiveInspections3-13-23-33-33-33-33-43-43-43-53-63-73-73-83-93-103-10File:NMP1PP3.WPD

NYNIAGARAUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999:;"";y4:,.>>>>',:"'.;";;;,',";"P";;.'>>,.;.;':;RECORD'.OF.:REVISION'",i:."':l,REVISION;"-,K>>.,',",':"'"DATE'.:-",":REASONFOR'REVISION~;-;,:-0September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionInterval~File:NMP1PP3.WPD

NVNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19993.0CLASS2SYSTEMS/COMPONENTSTheClass2SystemBoundariesweredevelopedbasedupontherequirementsofRegulatoryGuide1.26andtheNMP1FSAR.TheClass2componentsandsystems(includingsupports)subjecttoexaminationandtestingaredescribedindetailbelow:3.1ASMECodeExem'ptionsIWC-1220-Thefollowingcomponents(orpartsofcomponents)areexemptedfromthevolumetricandsurfaceexaminationrequirementsofIWC-2500;3.1.1IWC-1221-ComponentswithinRHR,ECCandCHRSystems(orportionsofsystems).(a)Vessels,piping,pumps,valves,andothercomponentsNPS4andsmallerinallsystemsexcepthighpressuresafetyinjectionsystemsofpressurizedwaterreactorplants.,(b)Vessels,piping,pumps,valves,andothercomponentsNPS1~/eandsmallerinhighpressuresafetyinjectionsystemsofpressurizedwaterreactorplants.(c)ComponentconnectionsNPS4andsmaller(includingnozzles,socketfittings,andotherconnections)invessels,piping,pumps,valves,andothercomponentsofanysizeinallsystemsexcepthighpressuresafetyinjectionsystemsofpressurizedwaterreactorplants.(d)ComponentconnectionsNPS1y2andsmaller(includingnozzies,socketfittings,andotherconnections)invessels,piping,pumps,valves,andothercomponentsofanysizeinhighpressuresafetyinjectionsystemsofpressurizedwaterreactorplants.(e)Vessels,piping,pumps,valves,othercomponents,andcomponentconnectionsofanysizeinstaticallypressurized,passive(i.e.,nopumps)safetyinjectionsystemsofpressurizedwaterreactorplants.(f)Pipingandothercomponentsofanysizebeyondthelastshutoffvalveinopenendedportionsofsystemsthatdonotcontainwaterduringnormalplantoperatingconditions.3.1.2IWC-1222-Componentswithinsystems(orportionsofsystems)otherthanRHR,ECCandCHRSystems(a)Vessels,piping,pumps,valves,andothercomponentsNPS4andsmaller.File:NMP1PP3.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003hlYNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999(b)ComponentconnectionsNPS4andsmaller(includingnozzles,socketfittings,andotherconnections)invessels,piping,pumps,valves,andothercomponentsofanysize.(c)Vessels,piping,pumps,valves,othercomponents,andcomponentconnectionsofanysizeinsystemsorportionsofsystemsthatoperate(whenthesystemfunctionisrequired)atapressureequaltoorlessthan275psigandatatemperatureequaltoorlessthan200degreesF.(d)Pipingandothercomponentsofanysizebeyondthelastshutoffvalveinopenendedportionsofsystemsthatdonotcontainwaterduringnormalplantoperatingconditions.3.1.3IWC-1230-ConcreteEncasedComponentsPipingsupportmembersandpipingsupportcomponentsthatareencasedinconcreteshallbeexemptedfromtheexaminationrequirementsofIWC-2500.3.2Component/PipingExaminationDevelopmentClass2componentssubjecttoexaminationareidentifiedinAppendixB.TheClass2SummaryTablessatisfytherequirementsofIWA-2420(a)(1)through(6)respectively.AnarrativediscussionofClass2componentssubjecttoexaminationandtestingaredescribedindetailbelow:3.2.1CategoryC-A,PressureRetainingWeldsinPressureVesselsScopeofExamination:100%ofallweldsatgrossstructuraldiscontinuitiesonly.Theexaminationsarelimitedtoonevesselamongagroupofvessels.NotapplicabletoNineMilePointNuclearPowerStationUnit1ie1Scopeofexamination:100%ofhead-to-shellwelds,(limitedto,onevesselofmultiplevessels)..NotapplicabletoNineMilePointNuclearPowerStationUnit1oWidScopeofexamination:100%ofTubesheettoshellwelds(limitedtoonevesselofmultiplevessels).Componentsapplicabletothisexaminationcategoryarethe(4)EmergencyCondenserHeatExchanger'(111,112,121,and122),and(4)ReactorContainmentSprayHeatExchanger's(111,112,121and122).File:NMP1PP3.WPD

LIVNlAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0CDate:September27,1999(16)C1.30ShellCirc.Welds,(4)weldsrequired3.2.2CategoryC-B,PressureRetainingNozzleWeldsInVesselsozVoaComponentsapplicableto(4)ReactorContainmentSprayHeatExchanger's(111,112,121,and122)..(8)C2.11NozzletoShellWelds,(2)requiredI22-ozzl~chesoifoVesComponentsapplicableto(4)EmergencyCondenserHeatExchanger's(111,112,121,and122).e221-zzIlScopeofExamination-Allnozzlesatterminalendsofpipingruns(limitedtoonevesselofmultiplevessels).Includesonlythosepipingrunsselectedfor.examinationunderExaminationCategoryC-F.(8)C2.21NozzletoShellorHeadWelds,(2)requiredIC222-NoadieoScopeofExamination-Allnozzlesatterminalendsofpipingruns(limitedtoonevesselofmultiplevessels).NotapplicabletoNineMilePointNuclearPowerStationUnit1~o~eTheEmergencyCondenserHeatExchangerNozzlesdonothaveinnerradiussections.IC2-RpceedoozzldVsScopeofExamination-Allnozzlesatterminalendsofpipingruns(limitedtoonevesselofmultiplevessels).NotapplicabletoNineMilePointNuclearPowerStation.22NooIIessibl'WelioVeNotapplicabletoNineMilePointNuclearPowerStation.C2-ozzieooeWoVFile:NMP1PP3.WPD

LIVNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ScopeofExamination-VisualVT-2oftelltaleholeinreinforcingplates(limitedtoonevesselofmultiplevessels).Examinationperformedinaccordancewithsystempressuretestprogram.NotapplicabletoNineMilePointNuclearPowerStation.3.2.3CategoryC-C,IntegralAttachmentsforVessels,Piping,Pumps&ValvesExaminationswillbeperformedinaccordancewiththealternaterequirementsofCodeCaseN-509,"AlternativeRulesfortheSelectionandExaminationofClass1,2and3IntegrallyWeldedAttachmentsSectionXl,Division1".ExaminationCategoryandItemNumbersshallbeasdefinedintheCodeCase.Haia2.InadditiontothoseconditionsspecifiedintheCodeCase:Aminimum10%sampleofintegrallyweldedattachmentsforeachitemineachCodeClassperintervalwillbeexamined.leuesseserIdchmen.ScopeofExamination-100%ofthelengthoftheattachmentweldofonlyoneintegrallyweldedattachmentofonlyoneofthemultiplevesselsselected.(8)C3.10IntegralWeldedAttachments,(1)requiredIrScopeofExamination-100%ofthelengthoftheattachmentweldof10%oftheweldedattachmentsassociatedwiththecomponentsupportsselectedforexaminationofcomponentsexaminedunderC-F-1andC-F-2.Multiplecomponentconceptisnotapplicable.(1031)Integrallyweldedattachments,(103)required-PuraIlWIScopeofExamination-100%ofrequiredareasofeachweldedattachment(limitedtoattachmentsofcomponentsexaminedperC-FandC-G).NotapplicabletoNineMilePointNuclearPowerStation.em-VavesInerailWeldeceScopeofExamination-100%ofrequiredareasofeachweldedattachment(limitedtoattachmentsofthosecomponentsrequiredtobeexaminedunderExaminationCategoriesC-FandC-G).File:NMP1PP3.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003MYNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999NotapplicabletoNineMilePointNuclearPowerStation.3.2.4CategoryC-D,PressureRetainingBolting>2"inDiameter10PrVScopeofExamination-100%boltsandstudsateachboltedconnectionofcomponentsrequiredtobeinspected.Theexaminationofboltingforvesselsmaybeperformedononevesselinagroupofvessels.ExcludedperIWC-2500-1size<2.0"Dia.ems4OC4&4NotapplicabletoNineMilePointNuclearPowerStation.3.2.5CategoryC-F-1,PressureRetainingWeldsinAusteniticStainlessSteelorHighAlloyPipingm1240C54&CWeldsareselectedforexaminationasdefinedbelow.RefertoAppendixBforasummarydetailofweldsselectedforexamination.(1)Requirementsforexaminationofweldsinpiping<NPS4applytoPWRhighpressuresafetyinjectionsystemsinaccordancewiththeexemptioncriteriaofIWC-1220.(2)Theweldsselectedforexaminationshallinclude7.5%,butnotlessthan28welds,ofallausteniticstainlesssteelofhighalloyweldsnotexemptedbyIWC-1220.(TheCategoryTotalincludespipetopipewelds,notexemptedbyIWC-1220,andarenotrequiredtobenondestructivelyexaminedperExaminationCategoiyC-F-1).Thesewelds,however,wereincludedinthetotalweldcounttowhichthe7.5%samplingratewasapplied).Thetotalweldsselectedforexaminationisbasedonaddingnon-exemptcircumferentialweldstoexcludedcircumferentialweldsandmultiplyingby7.5%.(72)C5.11Circ.Welds,(28)required(0)C5.41Circ.Welds,NotapplicabletoNMP1Theexaminationsshallbedistributedasfollows:(a)TheexaminationsshallbedistributedamongtheClass2systemsprorated,tothedegreepracticable,onthenumberofnon-exemptausteniticstainlesssteelorhighalloyweldsineachsystem(i.e.,ifasystemcontains30%ofthenon-exemptwelds,then30%ofFile:NMP1PP3.WPD

NVNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999thenondestructiveexaminationsrequiredbyExaminationCategoryC-F-1shouldbeperformedonthatsystem);(b)Withinasystem,theexaminationsshallbedistributedamongterminalendsandstructuraldiscontinuities[SeeNote(3)]belowprorated,tothedegreepracticable,onthenumberofnon-exemptterminalendsandstructuraldiscontinuitiesinthatsystem;and(3)(c)Withineachsystem,examinationsshallbedistributedbetweenlinesizesproratedtothedegreepracticable.Structuraldiscontinuitiesincludepipeweldjointstovesselnozzles,valvebodies,pumpcasings,pipefittings(suchaselbows,tees,reducers,flanges,etc.,conformingtoANSIB16.9),andpipebranchconnectionsandfittings.(4)~Theweldsselectedforexaminationshallbereexaminedduringsubsequentinspectionsovertheservicelifetimeofthepipingcomponent.3.2.6CategoryC-F-2,PressureRetainingWeldsinCarbonorLowAlloySteelPiping82Weldsareselectedasdefinedbelow.RefertoAppendixBforacompletesummaryofweldsselectedforexamination.(1)Requirementsforexaminationofweldsinpiping<NPS4applytoPWRhighpressuresafetyinjectionsystemsinaccordancewiththeexemptioncriteriaofIWC-1220.(2)Theweldsselectedforexaminationshallinclude7.5%,butnotlessthan28welds,ofallcarbonandlowalloysteelweldsnotexemptedbyIWC-1220.(SomeweldsnotexemptedbyIWC-1220arenotrequiredtobenondestructivelyexaminedperExaminationCategoryC-F-2.Thesewelds,however,shallbeincludedinthetotalweldcounttowhichthe7.5%samplingrateisapplied).Non-ExemptWelds(721)C5.51,Circ.Welds,(16)C5.52,Long.Welds,(0)C5.61,Circ.Welds,(0)C5.62,Longwelds,(0)C5.70,SocketWelds,(38)C5.81,Circ.Welds,(0)C5.82,LongWelds,(759),IncludesExcludedWelds(759)x7.5%=(56.9)or(57)minimumrequired,(66)scheduledFile:NMP1PP3.WPD

VNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999Theexaminationsshallbedistributedasfollows:(a)TheexaminationshallbedistributedamongtheClass2systemsprorated,tothedegreepracticable,onthenumberofnon-exemptcarbonandlowalloysteelweldsineachsystem(i.e.,ifasystemcontains30%ofthenon-exemptwelds,then30%ofthenondestructiveexaminationsrequiredbyExaminationCategoryC-F-2shouldbeperformedonthatsystem);(b)Withinasystem,theexaminationshallbedistributedamongterminalendsandstructuraldiscontinuities[SeeNote(3)below]prorated,tothedegreepracticable,onthenumberofnon-exemptterminalendsandstructuraldiscontinuitiesinthatsystem;and(c)Withineachsystem,examinationsshallbedistributedbetweenlinesizesproratedtothedegreepracticable.(3)Structuraldiscontinuitiesincludepipeweldjointstovesselnozzles,valvebodies,pumpcasings,pipefittings(suchaselbows,tees,reducers,flanges,etc.,conformingtoANSIB16.9),andpipebranchconnectionsandfittings.(4)Theweldsselectedforexaminationshallbereexaminedduringsubsequentinspectionintervalsovertheservicelifetimeofthepipingcomponent.(5)Onlythoseweldsshowingreportablepreservicetransverseindicationsneedtobeexaminedfortransversereflectors.RefertoAppendixBforacompletesummaryofweldsselectedanddistributedpereachsystemforexamination.3.2.7CategoryC-G,PressureRetainingWeldsinPumpsandValvessC6108C6ScopeofExamination-100%ofweldsinallcomponentsineachpipingrunexaminedunderExaminationCategoryC-F.ThisCategoryisapplicableto(4)ReactorContainmentSprayPumps(111,112,121,and122),and(4)ReactorCoreSprayPumps(111,112,121and122).Inthecaseofmultiplepumpsandvalvesofsimilardesign,size,function,andservice,theexaminationofonlyonepumpandonevalveamongeachgroupofmultiplepumpsandvalvesisrequired.Theexaminationmaybeperformedfromeithertheinsideoroutsidesurfaceofthecomponent.(80)C6.10PumpCasingWelds,(20)required(0)C6.20ValveCasingWelds,NotapplicabletoNMP1.File:NMP1PP3.WPD

hlYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999SubjecttoRequestforReliefISI-73.2.8CategoryC-H,AllPressureRetainingComponents0C72070ScopeofExamination-SystempressuretestsareconductedonallClass2systemsandcomponentsinaccordancewiththeNineMilePointUnit1SystemPressureTestingProgram,DocumentNMP1-PT-003.3.3SUCCESSIVEINSPECTIONSThesequenceofcomponentexaminationsestablishedduringthefirstinspectionintervalwillberepeatedduringthethirdinspectionintervai,totheextentpractical.File:NMP1PP3.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TABLEOFCONTENTSSECTION4-CLASS3SYSTEMSTableofContentsRecordofRevision4.0CLASS3SYSTEMS/COMPONENTS4.1ASMECodeExemptions4.1.1IWD-1220.14.1.2IWD-1220.24.2Component/SystemExaminationDevelopment4.2.1CategoryD-A4.2.2SystemPressureTests-Class34-14-24-34-34-34-34-34-34-4File:NMP1PP4.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003HVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999,';.RECORDOFREVISIONREVISION;;"-,::,-.-;,DATE';".,':AFFECTED';"~-"'i'!PAGESREASON',,FOR;REVISION0September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PP4.WPD

NineMilePointNuclearPowerStationUnlt1NMP1-ISI-003LlVNIAGARA1%UMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19994.0CLASS3SYSTEMS/COMPONENTSTheClass3systemboundariessubjecttoexaminationandtestingweredevelopedbasedupontherequirementsofRegulatoryGuide1.26,andtheNMP1FSAR.TheClass3componentsandsystemssubjecttoexaminationandtestingaredescribedindetailbelow:4.1ASMECodeExemptionsEmployed4.1.1IWD-1220.1Integralattachmentsofsupportsandrestraintstocomponentsthatare4"nominalpipesizeandsmallerwithinthesystemboundariesofExaminationCategoriesD-A,D-BandD-CofTableIWD-2500-1shallbeexemptfromthevisualexaminationVT-3,exceptfortheAuxiliaryFeedwaterSystem.4.1.2IWD-1220.2Integralattachmentsofsupportsandrestraintstocomponentsexceeding4"nominalpipesizemaybeexemptedprovided:~(a)Thecomponentsarelocatedinsystems(orportionsofsystems)whosefunctionisnotrequiredinsupportofreactorresidualheatremoval,containmentheatremoval,andemergencycorecooling;and(b)Thecomponentsoperateatapressureof275psigorlessandatatemperatureof200'93'C),orless.4.2Component/SystemExaminationDevelopmentClass3componentssubjecttoexaminationareidentifiedinAppendixC.TheClass3SummaryTablessatisfytherequirementsofIWA-2420(a)(1)through(6)respectively.AnarrativediscussionofClass3componentssubjecttoexaminationandtestingaredescribedindetailbelow:Note1:ExaminationCategoriesandExaminationItemNumbersforClass3IntegrallyWeldedAttachmentsaredefinedinaccordancewiththeASMECodeCaseN-509classificationcriteria.4.2.1CategoryD-AIntegralAttachmentsforClass3Vessels,Piping,PumpsssurVScopeofExamination-PerformVisual(VT-1)examinationof100%oftheweldlengthofallintegrallyweldedattachmentrequiredeachinterval.ApplicabletoEmergencyCondenserHeatExchanger's(111,112,121and122),ReactorBuildingClosedLoopCoolingHeatExchanger's(3),ShutdownCoolingWaterHeatFile:NMP1PP4.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003ElYNIAGARAI%UMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999Exchanger's(11,12,and13),SpentFuelPoolCoolingHeatExchanger's(11,and12).D1.10(28)IntegralAttachments,(9)requiredeDScopeofExamination-PerformVisual(VT-1)examinationof100%oftheweldlengtheachinspectioninterval(459)D1.20IntegralAttachments,(46)required.DIWScopeofExamination-PerformVisual(VT-1)examinationof100%oftheweldlengthofallrequiredintegrallyweldedattachmentseachinspectioninterval.(0)D1.30IntegralAttachments,notapplicabletoNMP1.D-VvWdeScopeofExamination-PerformVisual(VT-1)examinationof100%oftheweldlengthonallintegrallyweldedattachmentsrequiredfortheinspectioninterval.(0)D1.40IntegralAttachments,notapplicabletoNMP1Note2:Inthecaseofmultiplecomponentswithinasystemofsimilardesign,functionandservice,theintegralattachmentofonlyoneofthemultiplecomponentsshallbeexamined.ExaminationswillbeperformedinaccordancewiththealternaterequirementsofCodeCaseN-509,"AlternativeRulesfortheSelectionandExaminationofClass1,2and3IntegrallyWeldedAttachmentsSectionXI,Division1".InadditiontothoseconditionsspecifiedintheCodeCase,aminimum10%sampleofintegrallyweldedattachmentsforeachitemineachCodeClassperintervalwillbeexamined.Note3:IntegralAttachmenttoShockAbsorbersandsnubbersareincludedaspartofthepopulationforwhichthe10%sampleistaken.4.2.2SystemPressureTests-Class3ThepressureretainingcomponentswithintheboundaryofeachsystemspecifiedforExaminationCategoriesD-A,D-BandD-Carepressuretestedandvisuallyexamined(VT-2),forleakageinaccordancewiththeNineMilePointNuclearPowerStationUnit1SystemPressureTestProgram,documentNMP1-PT-003.File:NMP1PP4.WP0

NineMilePointNuclearPowerStationUnlt1NMP1-ISI-003hlVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TABLEOFCONTENTSSECTION5-COMPONENTSUPPORTSTableofContents.RecordofRevision.5.0CLASS1,2AND3COMPONENTSUPPORTS-IWF5.1SupportsExemptFromExamination5.2SupportExaminationDevelopment5.2.1Class1ComponentSupports5.2.2Class2ComponentSupportsI5.2.3Class3ComponentSupports5.3NarrativeDiscussion5.3.1ExaminationCategoryF-ASupports.5.4Snubbers~~~~~~~~~~515-25-35-35-35-35-35-35-45-45-5Fi!e:NMP1PP-5.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElYNIAGARA1%UMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999;REVISION,NO,"DATE'.'RECORD'OFREVISION;AFFECTED'AGES",REASONFORREVISION:-""+;,'-;.-':,"September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PP-5.WPD

ElVNIAGARAHUMOHAWKNirieMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19995.0CLASS1,2AND3COMPONENTSUPPORTS-IWFComponentsupportsselectedforexaminationshallbethesupportsofthosecomponentsthatarerequiredtobeexaminedunderIWB,IWCandIWD.NMPCwillconductexaminationsinaccordancewithalternateexaminationrequirementsofCodeCaseN-491-1,"AlternativeRulesforExaminationofClass1,2,3andMCComponentSupportsofLight-WaterCooledPowerPlants,SectionXI,Division1",asnotedbelow:AsanalternatetotheClass1,2and3ComponentSupportRequirementsofTableIWF-2500-1,NMPCwillperformthefollowing:Class1,2and3supportsreceiveaVisual(VT-3)examinationtodeterminetheirgeneralmechanicalandstructuralcondition,andwhenrequired,conditionsrelatingtotheiroperability.ThesupportssubjecttoexaminationhavebeenselectedinaccordancewithCodeCaseN-491-1.(RefertoAppendixDforDetailTables).5.1SupportsExemptFromExaminationExemptionsareasstatedinIWB-1220,IWC-1220andIWD-1220,(Sections2,3and4ofthisProgram,respectively).a.Inaddition,portionsofsupportsthatareinaccessiblebybeingencasedinconcrete,buriedunderground,orencapsulatedbyguardpipearealsoexemptfromtheexaminationrequirements.b'.NMPChasdeterminedthatasupportthatdoesnotfullymeetthedefinitionofacomponentsupport,asdefinedwithinASMESectionXI,ArticleIWA-9000,GlossarydefinitionforComponentSupport,isexemptforexamination.Pipewhiprestraints,insulationlugs,orunusedpipesupports,whichdonotprovidestructuralstabilityorsupporttheweightofthepipe,areexempt.5.2SupportExaminationDevelopment5.2.1Class1ComponentSupportsClass1componentsupportssubjecttoexaminationareidentifiedinAppendixD.5.2.2Class2ComponentSupportsClass2componentsupportssubjecttoexaminationareidentifiedinAppendixD.5.2.3Class3ComponentSupportsClass3componentsupportssubjecttoexaminationareidentifiedinAppendixD.TheClass1,2and3SummaryTablessatisfytherequirementsofIWA-2420(a)(1)through(6)respectively.File:NMP1PP-S.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003NVNIAGARAklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19995.3NarrativeDiscussionAnarrativediscussionofClass1,2and3componentsupportssubjecttoexaminationaredescribedindetailbelow:InordertoassurethatarepresentativesampleofsupportswithineachCodeClassisexamined,(CodeExaminationCategoryF-A,ExaminationItemNumbersF1.10Class1,F1.20Class2,F1.30Class3,andF1.40otherthanpiping),selectionwasbasedonClass,SystemandType,totheextentpractical'.Exam.ItemNo.ASMECodeClassTable5-1CATEGORYF<<ASELECTIONPROCESSApplicableSystemTypeofSupportsF1.10F1.20F1.30F1.40CodeClass1CodeClass2CodeClass3Otherthanpiping44.2ControlRodDrive39.0EmergencyCondenser31.0Feedwater42.1LiquidPoison01,02,03.0MainSteam33.0ReactorCleanUp40.0ReactorCoreSpray32.0ReactorRecirculation38.0ReactorShutdownCooling80.0ReactorContainmentSpray54.0SpentFuelPoolCooling72.0ServiceWater70.0ReactorBuildingCloseLoopCoolinga.b.C.d.e.f.g.RodHangersAnchorsSpringsStanchionsSwayBracesDeadWeightSnubbers5.3.1ExaminationCategoryF-ASupportsScopeofExamination-VisualVT-3examinationof25%ofallnon-exemptClass1Supports.(190)F1.10Supports,(48)requiredAIIcomponentsupportssubjecttoexaminationhavebeenclassified(a,b,c,d,etc.),totheextentpractical.Asthesesupportscouldbeclassifiedbyoneormoreofthesuffixesforthesamesupport,onlyonesuffixwasselected.Theseclassificationsareidentifiedinthe10-yearInspectionTables.File:NMP1PP-S.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999ScopeofExamination-VisualVT-3examinationof15%ofallnon-exemptClass2Supports.(433)F1.20)Supports,(65)required3ScopeofExamination-VisualVT-3examinationof10%ofallnon-exemptClass3Supports(503)F1.30Supports,(50)requiredScopeofExamination-VisualVT-3examinationof100%ofallnon-exemptSupports,otherthanpipingsupports.ThisitemisapplicabletotheEmergencyCondenserHeatExchanger's(111,112,121,and122);EmergencyServiceWaterPump(11and12);ReactorBuildingClosedLoopCoolingHeatExchanger,PumpandMUTank;ReactorContainmentSprayHeatExchanger's(111,112,121and122);ReactorContainmentSprayandRawWaterPumps(111,112,121and122);ReactorCoreSprayPumps111,121and122)andReactorCoreSprayToppingPumps(111,112,121and122);ReactorRecirculationPumps(11,12,13,14and15);ReactorVesselSupports;ShutdownCoolingWaterHeatExchanger,(11,12,and13);SpentFuelPoolCoolingFilter(11and12);SpentFuelPoolCoolingHeatExchangerandPumps(11and12)andtheSpentFuelPoolCoolingSurgeTank.Formultiplecomponents,onlyoneofthemultiplecomponentsarerequiredtobeexamined.(89)F1.40Supports,(26)requiredNote1:TherecordingofHotorColdpositionswillbeperformedinconjunctionwiththeVT-3examination.5ASnubberExaminationandPerformanceTestingProgramThefollowingsectionprovidesadescriptionofNineMilePointUnit1SnubberProgramforExaminationandPerformanceTestingofDynamicRestraints(Snubbers).TheSnubberProgramiscurrentlydefinedinplanttechnicalspecification,amendment142,section4.6.4,andappliestothevisualinspectionandperiodictestingrequirementsforshocksuppressors(snubbers),byassuringthesnubbersperformtheirintendedfunction.Exclusionsfromtheinspectionprogramarethosesnubbersthatareinstalledonnonsafety-relatedsystemsandthenonlyiftheirfailureorfailureofthesystemonwhichtheyareinstalled,wouldhavenoadverseeffectonthesafety-relatedsystem.ScopeofExamination-Snubbersarecategorizedintotwotypes(mechanicalandhydraulic),andFile:NMP1PP-S.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElYNIAGARAaUmoHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999classifiedasaccessibleorinaccessible.AlthoughsnubbersarelistedwithintheISIProgramaspartofthetotalpopulationforwhichthepercentageofCodeCaseN-491-1weretaken,nosnubbersarescheduledandnoCodecreditisbeingtakenforsnubberexaminationswithinthisprogram.SnubbersinspectionsareperformedbytheplantmaintenanceorganizationinaccordancewithPlantTechnicalSpecificationandarevisually(VT-3)inspectedinaccordancewiththefollowingschedule.Table5-2VISUALINSPECTIONFREQUENCYNumberofsnubbersfoundinoperable'duringinspectionor-duringinspection...,.interval3,45,6,78ormoreNextrequiredinspectionintervalRefuelingPeriod12months*25%6months*25%124days~25%62days*25%31days~25%Therequiredinspectionintervalshallnotbelengthenedmorethanonestepatatime.ScopeofTesting-Atleastonceeachrefuelingcycle,10%ofthetotalpopulationofeachtype(mechanicalorhydraulic),(accessibleorinaccessible)ofsnubbersintheplantshallbefunctionallytested.TestingrequirementsshallbeinaccordancewithPlantTechnicalSpecificationrequirements.ThePreseviceExaminationRequirementsdetailedinOMa-1988Part4,Para.2.2ThermalMovementExaminationhavebeenevaluatedandconsideredpreoperationalconstructionrequirementsnotapplicabletotheNMP1SnubberProgram.SnubberProgramcomplianceforgeneralandspecificrequirementsalongwithexemptionsfromOMa-1988Part4willbedefinedwithinapplicableplantprocedures.RelieffromspecificrequirementswithinOMa-1988Part4,arelocatedinAppendixF,ReliefRequestISI-9.File:NMP1PP-5.WPD

ElYNlAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContentsRecordofRevisionTABLEOFCONTENTSSECTION6-AUGMENTEDEXAMINATIONS6-16-46.0AUGMENTEDEXAMINATIONS6.1.RegulatoryDocuments6.1.1USNRCRegulatoryGuide1.65ClosureHeadStuds.~............6-56-56.56.1.2USNRCRegulatoryGuide1.150UltrasonicExamination~.~...~...~~.......6-56.1.3GenericLetter88-01IGSCCCrackinginPiping..6.1.4GenericLetter94-03IGSCCCrackingofCoreShrouds,BWRVIP076.1.5GenericLetter98-05ReactorVesselShellWeldsBWRVIP056-56-146-156.1.6NUREG0619BWRFeedwaterNozzleandCRDReturnLineNozzleCracking...6-156.1.7NUREG0803,GL81-34,86-01BWRScramSystemPipeBreak..6.2IndustryDocuments6.2.1In-VesselVisualExaminations6.2.2SIL571InstrumentNozzleSafeEndCrackingBWRVIP06,27,496.2.3SIL409,RICSIL073IncoreDryTubeCracks..~..6.2.4SIL419CRDHydraulicControlValves.6.2.5SIL433ShroudHeadBoltCracks6.2.6SIL455,RICSIL072AIloy182NozzleWeldments6.2.7SIL474SteamDryerDrainChannelCracking~6.2.8SIL483CRDCapScrew.6.2.9SIL539RPVHeadCladCracking6-206-206-206-226-246-246-246-256-266-276-27File:NMP1PP6.WPD

ElVNIAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContents-Continued6.2.10SIL554TopGuideCracking6.2.11SIL588TopGuideandCorePlateCracking.6.2.12SIL459RecirculationPumpShaftCracking.6.2.13IEBulletin80-13,RICSIL073CoreSpraySparger.6.2.14IEBulletin96-03EmergencyCoreCoolingSuctionStrainers.6.3AdditionalCommitments6.3.1NCTS503783-01CRDHousings.6.3.2INPOSER5-85MixingPointsListofTables6.1IGSCCCategoryAWeldsSelected.6.2.IGSCCCategoryDWeldsSelected6.3IGSCCCategoryEWeldsSelected6.4IGSCCCategoryFWeldsSelected6.5IGSCCCategoryGWeidsSelected~.6.6IGSCCCategorySWeldsSelected..6.7IGSCCExaminationRequirements6.8RoutineInspectionIntervalsRefuelingCycles.~..~6.9FeedwaterNozzle/SpargerInspectionRecommendations6.10AugmentedFeedwaterNozzleExaminations..6.11In-VesselAugmentedExaminations(BWRVIP's)6.12InstrumentNozzies6-276-286-286-296-306-316-316-346-76-86.116.126-126-136-146-176-176-186-206-226.13InstrumentNozzles6.14InstrumentNozzles6.15IRMIncoreDryTubeAssembly.6-236-236-24File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnlt1NMP1-ISI-003MVNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TableofContents-Continued6.16SIL455SelectedWelds6.17SIL474SteamDryer6.18RPVHeadCladding.6.19UpperCoreGrid6.20SIL588UpperCoreGrid6.21SIL459PumpShaft6.22CoreSpraySparger6.23IEB96-03SuctionStrainers6.24CRDHUpperJWelds.6.25TeeBaseMaterial6-256-276-276-286-286-296-306-306-316-34ListofFigures6.3FeedwaterNozzleExaminationZones.6-19File:NMP1PP6.WPD

ElYNIAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REVISIONNo.RECORDQFREVISIONREASONFORREVISIONSeptember27,1999EntireDocumentUpdatedlnserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19996.0AUGMENTEDEXAMINATIONSThissectionoftheThirdInserviceInspectionProgramprovidesasummarydescriptionofadditionalrequirementsidentifiedinregulatory,industryorotherdocumentsinadditiontotheASMECode.NMPChasreviewedtheseadditionaldocumentsforconsiderationandweredeterminedtobeapplicablehaveincorporatedthemwithintheThirdInserviceInspectionPlanTables.NMPCplansonutilizingwhereapplicable,AugmentedExaminationstosatisfytherequirementsofASMESectionXI.6.1REGULATORYDOCUMENTS6.1.1USNRCRegulatoryGuide1.65-MaterialsandInspectionsforReactorVesselClosureStuds.Thisregulatoryguidedefinesmaterialsandtestingproceduresacceptabletotheregulatorystaffforimplementingmaterialandexaminationcriteriaforreactorvesselclosureheadstudsforlight-water-cooledreactors.CurrentlytheASMECode,SectionXIrequiresavisualexaminationtobeperformedonnuts;avolumetricexaminationtobeperformedonstuds,inplace;andbothavolumetricandasurfaceexaminationwhenthestudisremoved.AtNMP1thereactorpressurevesselstudsarenotremoved.ScopeofExamination-Thesixty-four(64)closureheadstudsreceiveanultrasonicexaminationofeachstud,in-place.AsrequiredbytheCode,approximatelytwenty-two(22),(1/3ofthe64studs)willbeexaminedin-placeeachperiod.RegulatoryPositionC.4.bwillbeinvokedtoexaminebyeitheramagneticparticleorliquidpenetrantmethodarepresentativesampleofaminimumoftwelve(12)studsandonareasonablegeometricdistributionofthree(3)studspereach90-degreequadrant.Additionally,NMP1willremove12studsperinterval,essentially4perperiod,withadistributionof3per90-degreequadrant.Thesestudsreceivebothavolumetricandasurfaceexamination.(64)ClosureHeadStuds,(12)required,(4)perPeriod6.1.2USNRCRegulatoryGuide1.150-UTofRPVWeldsduringPSIandISIThisregulatoryguideidentifiestheacceptablemethodsofperformingultrasonicexaminationofReactorPressureVesselwelds.NMP1deviatesfromtheguidebyperformingexaminationsoftheRPVshellweldsincompliancewiththespiritofPDIandSectionXI,AppendixVill.ScopeofExamination-ExcludedfromtheThirdInserviceInspectionIntervalbyReliefRequestISI-1.6.1.3GenericLetter88-01,AugmentedIGSCCExaminationsTheNineMilePointTechnicalSpecifications,Section4.6.F.3,requiresNMPCtoimplementanaugmentedinspectionprogramforthoseweldsdesignatedasIGSCCsusceptible.TherequirementsforanaugmentedIGSCCinspectionprogramaremandatedbyGenericLetterGL88-01,GL88-01Supplement1,"IntergranularStressCorrosionCrackinginBWRAusteniticStainlessSteelPiping"andNUREG-0313,Revision2,"TechnicalReportonMaterialSelectionandProcessingGuidelinesforBWRCoolantPressureBoundaryPiping."Fiie:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003hlVN1AGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999GenericLetter88-01,USNRCPositiononIGSCCinBWRAusteniticStainlessSteelPiping,presentstheUSNRCstaffpositionsonmaterials,processes,waterchemistry,weldoverlayreinforcement,partialreplacement,stressimprovementofcrackedweldments,clampingdevices,crackcharacterizationandrepaircriteria,inspectionmethodsandpersonnel,inspectionschedules,sampleexpansion,leakdetection,andreportingrequirements.ThetechnicalbasesforthesepositionsaredetailedinNUREG-0313,Rev.2,"TechnicalReportonMaterialSelectionandprocessGuidelinesforBWRCoolantPressureBoundaryPiping."GenericLetter88-01,Supplement¹1-InitsfirstsupplementtoGL88-01,issuedFebruary2,1992,theUSNRCprovidedseveralacceptablealternativestaffpositionstothoseoriginallyintheGenericLetter.NMP1haselectedtousetwoofthesealternativestaffpositions.OneofthesepositionsallowssampleexpansionforCategoryDweldstobelimitedtothepipingsystemwherethecrackwasfound.NMP1haselectedtoexamine50%ofCategoryDwelds,bysystemloop,eachcycleandwillusethisrelaxationofsampleexpansioncriteriashouldcrackingbefound.ThesecondpositionisdescribedinExaminationCategorySbelow.NMP1Background-In1981NMP1identifiedIGSCCinlargeboreausteniticstainlesssteelpipingandreplacedthepipingwithlowcarbonausteniticstainlesssteel.NMPCconsidersthereplacementmaterialtobeIGSCCresistantmaterial,CategoryA,asdefinedinGL88-01.ExaminationsperformedunderthescopeofGL88-01(andthisprogramplan)areincompliancewith1989EditionofASMESectionXI.Inaddition,asrequiredbyNMP1TechnicalSpecification4.2.6a.2,"theInserviceInspectionProgramforpipingidentifiedinUSNRCGenericLetter88-01shallbeperformedinaccordancewiththestaffpositionsonschedule,methods,personnelandsampleexpansionidentifiedinGL88-01."WherepracticalexaminationsperformedonIGSCCweldsshallalsobeusedtosatisfySectionXIProgram"B"compliance.GL88-01dividespipingweldsinto7categoriesletteredAthroughG,ofwhichfourareapplicabletoNMP1.TheyarecategoriesA,D,FandG.AsummaryofthesecategoriesaswellastheirapplicabilitytoNMP1isshowninapplicableTableidentifiedbelow.IGSCCCategoryAWeldments-Identifiesweldswhicharefabricatedfromresistantmaterials.CategoryAweldmentsarethoseweldswithnoknowncracks,thathavealowprobabilityofincurringIGSCCproblems,becausetheyaremadeentirelyofIGSCCresistantmaterialorhavebeensolutionheattreatedafterwelding.AugmentedexaminationsrequiredbyGL88-01areidentifiedintheThirdInserviceInspectionPlanandScheduleTables.ScopeofExamination-IGSCCCategoryAweldsareexaminedinaccordancewithaschedulesimilartothatcalledoutforinSectionXI.A25%sampleofweldsshallbeexaminedduringthisinspectionintervalwithatleast12%in6years.Thereareonehundredforty-one(141)Category"A"weldsatNMP1,onehundredthirty-one(131)areASMEClass1andten(10)weldsareASMEClass2.(141)CategoryAWelds,(35)requiredFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003hlTNlAGARAHklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999,.:-',"';:188CC";Category"A"'WeldsS~lected.-.'='::ComponentIdentifloafionComponentDescriptionPeriodSelect'edComponent-','ComponentIdentification'..;.DescriptionPeriodSelected,',;32-WD-02232-WD-03532-WD-040P-VV-PE-P2~oPERIOD32-WD-1253"PERIOD32-WD-128A2"oPERIOD32-WD-167N1D-SEP-VN1E-SE3"PERIOD2"PERIOD1sPERIOD32-WD-04132-WD-04232-WD-061P-N2AN2A-SEE-P2"PERIOD33-WD-0153"PERIOD33-WD-035P-VINACC.V-PINACC2"PERIOD32-WD-171BRV-R3"PERIODEachOutageEachOutage32-WD-08232-WD-11032-WD-12132-WD-12232-WD-16432-WD-20832-WD-002N2BSE-NP-EP-N2CSEN2CSE-NN2DSE-NN2ESE-NN1A-SE3"PERIOD39-WD-0023oPERIOD39WD0031PERIOD39-WD-0061~PERIOD39-WD-0082"PERIOD39-WD-0093"PERIOD39-WD-0972"PERIOD39-WD-211C1N5A-SENSASE-PP-PP-PP-VINACCP-VINACCP-E1sTPERIOD1PERIOD1sTPERIOD1sPERIODEachOutageEachOutage2"PERIOD32-WD-04532-WD-08532-WD-09239-WD-121C1*N1B-SEN1C-SEP-EP-HX1~PERIOD39-WD-100"R-P1sTPERIOD39-WD-117C1'-E3"oPERIOD39-WD-037C1'-E1~PERIOD39-WD-041C1*P-HX2"PERIOD3oPERIOD1~PERIOD3"PERIOD32-WD-06232-WD-11932-WD-157P-VP-EV-P3"PERIOD32-WD-1011~PERIOD32-WD-1203"oPERIODP-PE-P1sTPERIOD1PERIOD*Class2weldsIGSCCCategoryBWeldments-Identifiesweldswhicharefabricatedfromnon-resistantmaterialCategoryBweldmentsarethoseweldsmadeofresistantmaterials,buthavehadanSlperformedeitherbeforeserviceorwithintwoyearsofoperation.File:NMP1PP6.WPD

YNIAGARA4MOHAWKNineMilePointNuclearPowerStationUnlt1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ScopeofExamination-TherearenoweldsinthiscategoryattheNineMilePointNuclearPowerStation.IGSCCCategoryCWeldments-Identifiesweldswhicharefabricatedfromnon-resistantmaterials.CategolyCweldmentsarethoseweldsnotmadeofresistantmaterials,andhavebeengivenanSlprocessaftermorethantwoyearsofoperation.ScopeofExamination-TherearenoweldsinthiscategoryattheNineMilePointNuclearPowerStation.IGSCCCategoryDWeldments-non-resistantmaterials:nostressimprovementCategoryDweldmentsarethoseweldsnotmadewithresistantmaterials,andhavenotbeengivenanSltreatment,buthavebeenexaminedandfoundtobefreeofcracks.Includedinthiscategoryareallbimetallicnozzleweldmentsmadewithnon-resistantmaterialand182inconelweldbutter.ScopeofExamination-Allweldsshallbeexaminedatleasteverytworefuelingoutages.Approximately50%ofallCategoryDweldsshallbeexaminedeachrefuelingoutage.WeldsclassifiedascategoryDareexaminedinaccordancewithGL88-10,Table1,asmodifiedbyalternativestaffposition¹4forsampleexpansion,ascontainedinSupplement1toGL88-01.All142CategoryDweldsareultrasonicallyexaminedeveryotherrefuelingoutage,withsampleexpansionlimitedtothepipingsystemloopwherecrackingwasfound.(142)CategoryDWelds,(284)requiredTabie6-2IGSCCCategory"D"SelectedWeIdsComponentIdentification33-WD-00433-WD-04633-WD-04937-WD-00338-WD-00138-WD-00238-WD-00338-WD-00438-WD-00538-WD-00638-WD-089ComponentDescrfptionP-PP-PP-EF-RV-PP-EE-EE-PP-EE-PP-EComponentIdentification40-WD-38A40-WD-03940-WD-04140-WD-04340-WD-043A40-WD-04440-WD-04540-WD-04740-WD-04840-WD-04940-WD-051ComponentDescriptionN6ASE-SEN6AN-SEV-PBCP-NP-EE-PP-VP-EE-VP-EFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003NVNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999"':.'":'-:':-.7j-:,'.,:::;;;-;-',".",.:-';>>'""'::';""::":-"IGSCC'Catgory.'"'SelectecfVfeids",:,-",.'".'-.',-",,'~,"-,.~;:,.";:'Comporient:Identification38-WD-09038-WD-09138-WD-09238-WD-09338-WD-09439-WD-19539-WD-19639-WD-19739-WD-19839-WD-19939-WD-20039-WD-20139-WD-20239-WD-203R39-WD-204A39-WD-204R39-WD-226B39-WD-22739-WD-22839-WD-22939-WD-23039-WD-23139-WD-23239-WD-23339-WD-233ACo'mporiant:.:;."Description,::E-PP-PP-PP-EE-VP-EE-PP-EE-PP-EE-PP-EE-PP-EP-PE-PP-PP-EP-EP-EE-PP-PP-EE-PP-EComponent,identification'0-WD-05240-WD-05340-WD-05440-WD-05540-WD-05640-WD-05840-WD-05940-WD-06040-WD-06140-WD-06240-WD-06340-WD-06440-WD-06540-WD-06640-WD-06740-WD-06840-WD-06940-WD-07040-WD-07240-WD-07340-WD-07440-WD-07540-WD-07640-WD-07740-WD-079Compcinent,DescriptionE-PP-EE-PP-EE-PP-TT-VV-PP-EE-PP-EE-PP-EE-PP-TT-PP-VV-PE-PP-TT-PP-PP-RR-PN6BSE-EFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003HYNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999...-Tabte,.s,'-,,2"~.:;.'.;;:;,:,';::,",,,.;;:,lGSCC;Categorjj.".0,"...,':;Sefectecf.,:,Nelds.:...,:,;,.,:j;;;:,;;~,",',;;,,'Component'Iclentiffcation'"',""Component~"':.Coinponentfdentiftcation:.,Descrtptlon';:;:~;;;,;;:,':,~,',,;;,rCornponent"'"'"<<Description':"39-WD-234A39-WD-235R39-WD-09040-WD-00140-WD-00340-WD-00440-WD-00540-WD-00640-WD-00740-WD-00840-WD-00940-WD-01140-WD-01240-WD-01340-WD-01440-WD-01540-WD-01640-WD-01740-WD-01840-WD-02040-WD-02140-WD-02240-WD-02340-WD-02440-WD-025P-EE-PN5B-SEV-PBCP-EE-PP-PP-VP-EE-VP-EE-PP-PP-PP-EE-PP-EE-PP-TT-PP-EE-PP-VV-E40-WD-079A40-WD-08039-WD-01439-WD-01639-WD-01739-WD-02039-WD-02139-WD-02239-WD-02439-WD-02539-WD-02639-WD-02739-WD-03039-WD-03439-WD-03539-WD-03839-WD-10239-WD-10439-WD-10539-WD-10839-WD-10939-WD-11039-WD-11239-WD-11339-WD-114N6BSE-SEN6BN-SEP-PP-PP-PP-PP-PT-PT-PE-PP-PP-PE-PP-PP-PE-PP-PP-PP-PP-PP-TT-PT-EE-PP-PFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003LIVNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999,,IGSCC,Category",9"Selected'eids...:.:,',",ComsonantIdentification40-WD-02640-WD-02740-WD-02840-WD-02940-WD-03040-WD-03140-WD-03240-WD-03340-WD-03440-WD-035ComponentDescriptionE-PP-TT-VV-PP-TT-PP-EE-EP-EE-RComponentIdentfffcatfon'?oA,>39-WD-11539-WD-11839-WD-12239-WD-12339-WD-12439-WD-12539-WD-12839-WD-12940-WD-03640-WD-038ComponentOescriptfonP-EE-PP-EP-PP-EE-PE-PP-PR-PN6ASE-EIGSCCCategoryEWeldments-Allweldsincludedlnthiscategoryareweldoverlays.CategoryEweldmentsarethoseweldswithknowncracksthathavebeenreinforcedbyanacceptableweldoverlayorhavebeenmitigatedbyanSltreatmentwelding.ScopeofExamination-shouldbeinspectedonceeverytworefuelingoutagesafterrepair.Approximately50%shallbeinspectedduringthefirstrefuelingoutageandsubsequentoutages.(1)CategoryEwelds,(1)requiredonceeverytworefuelingoutagesTABLES@"IGSCC:,CATEGORY"E"SELECTEOWELDS.".>>",'OMPONENT:'"':IDENTIFICATION33-FW-22COMPONENT,DESCRIPTIONPIPETOSSNOZZLE2REMARKS"'.'::~-':::"OutsideCIV,10%eachrefueling,weldoverlay,onceevery2RFO'sIGSCCCategoryFWeldments-Cracked,inadequateornorepairCategoryFweldmentsarethoseweldswithknowncracksthathavebeenapprovedbyanalysisforlimitedadditionalservicewithoutrepair.File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003hlVNlAGARAHklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999ScopeofExamination-inspectedeachrefuelingoutages.(5)CategoryFwelds,(5)requiredeachrefuelingoutage.,,"IGSCCCategor'y",F",Selected'Vfeldi'"WeldNo,.'..,"32-WD-04632-WD-05032-WD-08632-WD-12632-WD-168Component'identification..'",NozzleN1BSafeEnd-ElbowValve32-376-PipeNozzleN1CSafeEnd-ElbowNozzleN1DSafeEnd-ElbowNozzleN1ESafeEnd-ElbowRe-.eximlnatlon'Frequency':,"';,,;ExamineeachrefuelingoutagePerIWB-2420(b)eachperiodExamineeachrefuelingoutageExamineeachrefuelingoutageExamineeachrefuelingoutageIGSCCCategoryGWeldments-Non-resistantandnotinspectedbyUTCategoryGweldmentsarethoseweldsnotmadeofresistantmaterials,havenotbeengivenanSltreatment.ScopeofExamination-WeldsclassifiedasCategoryG(excludingRWCUseeGL88-01Supplement¹1)areexaminedinaccordancewithGL88-01.Twenty-seven(27)RWCUpipingweldsareincludedinthiscategory,two(2)ofwhichareinsidepenetrations,one(1)examinedevery2refuelingoutagesandtwenty-four(24)arepartoftheLevel2expandedsample~Anadditionaltwelve(12)welds,seven(7)ofwhichareinsidepenetrationsandfive(5)cannotbeexaminedduetoconfiguration,receiveavisualexaminationforevidenceofleakageateachrefuelingoutage.(39)CategoryGwelds,(15)required.,'.;,Table6<<8~;~lGSCC'Category"6"Selected~'.WelCh:.',",'Component...-.':,Identlffcation,:;,Coinpon'e'nt~.'""',Descriptton"P'~,!Exa'mtnatio'n'.,:.'omp'oiient::.:Requirements,'.".;,,IdentltIc'ation,',',:,Com'poneatExamin'ation":~D'es'crlption,,,,Requtremerits",;.;33-WD-01433-WD-03633-WD-22R38-FW-007P-PP-EP-NP-PInacc.VT-2eachoutageInacc.VT-2eachoutage2Noand3RoPeriodInacc.VT-2eachoutage38-WD-08738-WD-08839-WD-19439-WD-194AV-PP-PV-PP-PInacc.VT-2eachoutageInacc.VT-2eachoutageVT-2eachoutageInacc.VT-2eachoutageFile:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003alVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999>Co'mpone'nt:-:,:.,',':Component-.;';Examfnition,'.'.Identification:-".--'Description',:'Requirements;.Compoiient-:...:Component:.Identification-DescrIptionExaminationRequirements38-FW-00839-WD-226AP-Vp-pInacc.VT-2eachoutageInacc.VT-2eachoutage39-WD-22639-09R-WD-001V-PV-EWVT-2eachoutageVT-2eachoutage39-10R-WD-00140-WD-050AV-EV-PVT-2eachoutageVT-2eachoutage40-WD-010AV-PInacc.VT-2eachoutageIGSCCCategorySWeldments-outboardofCl'sCategorySweldmentsarethoseweldsthatarelocatedontheReactorWaterCleanUpsystemoutboardoftheContainmentIsolationValve.ScopeofExamination-TheReactorWaterCleanupSystemoutsideofthecontainmentisolationvalveshasveryhighlevelsofradiation.ThereforeuntilactionsassociatedwithGL89-10onmotoroperatedvalvesarecompletedbylicensees,(ref.filecodeM96-0007andM96-0016)theUSNRCstaffhasdeterminedthattheinspectionofthesubjectpipingonasamplingbasisofatleast10%oftheweldpopulationmaybeperformedeachrefuelingoutage.ThepopulationofRWCUpipingthatliesoutboardofcontainmentisolationvalvesis32.Basedonthe10%samplerequirement,NMP1willexaminethree(3),(10%of32)weldseachoutage.(6)IGSCCCategolySwelds,(3)requiredeachrefuelingoutage.'Table6A',-IGSCCiCategory"S"Setected:Welds'...+'eldNumber'-,;.'-'-,,*-'.-'omponent'Description-'xamlnatioriFrequency33-FW-3533-FW-3633-FW-37Elbow-NozzleNozzle-ElbowElbow-NozzleEachRefuelingOutageEachRefuelingOutageEachRefuelingOutageInspectionSchedule-TheextentandfrequencyofinspectionforvariousweldmentcategoriesaredetailedinTable6-6below.File:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003EIYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999.TABLE6 ;:.".;,-",:-";:"-.::.;::;,::-',:;"lGSCCEXAMINATfONREQUlREMENTS,'GSCCCATEGORY:ADGS"'.':.'XA'MINATION,,'>>REQUIREMENTS25%50%AllAllAllAllAllEXTENTOF.,EXAMINATION,Every10YearIntervalEvery10YearIntervalWithinTwoRefuelingCyclesafterthePost-SlInspection,andAllEvery10YearsthereafterEveryTwoRefuelingOutageEveryTwoRefuelingOutagesEveryRefuelingOutageNextrefuelingOutageEachrefuelingOutageREMARKSAtleast12%in6yearsAtleast25%in6yearsAtleast50%in6years50%eachrefuelingoutage50%eachrefuelingoutageAllduetoinaccessibilityandhighradiationRWCUoutboardofCIV'sSampleExpansion-IfoneormorecrackedweldsinIGSCCCategoriesA,B,orC,arefoundbyasampleinspectionduringtheThirdTen-YearInterval,anadditionalsampleofweldsshouldbeinspected.SpecificexpansionrequirementsforIGSCCweldsaredefinedinSection8.0.6.1.4GenericLetter94-03,"IntergranularStressCorrosionCrackingofCoreShroudsinBWRs"andBWRVIP-07,"EPRIReportTR-105747GuidelinesforReinspectionofCoreShrouds.InSeptember1994,theUSNRCissuedGL94-03,whichrequiredthatallBWRlicenseesinspecttheircoreshroud.InresponsetoGL94-03NMP1electedtopre-emptivelyrepairthecoreshroudinlieuofinspection.ThisrepairinstalledstabilizerassembliesthatreplacedtheloadcarryingcapabilityoftheshroudcircumferentialweldsH1throughH7.ByletterdatedMarch31,1995,theUSNRCrequestedNMP1tosubmitreinspectionplansforthecoreshroudanditsrepairassemblies.ReinspectionplansweresubmittedinDecember1998whichwereconsistentwiththeguidelinesprovidedinBWRVIP-07,EPRIReportTR-105747,"GuidelinesforReinspectionofBWRCoreShrouds.InaletterdatedMarch24,1999,theUSNRCtransmittedanSERwhichacceptedtheNMP1inspectionplanssubmittedintheDecember30,1998NMPCletter.TheseplanswereacceptedforRFO-15only.ShroudverticalweldswereinspectedduringRFO-14andRFO-15.DuringRFO-15shroudverticalweldsV9andV10wererepaired.FutureinspectionsofthecoreshroudanditsrepairassemblieswillbeperformedinaccordancewiththeinspectionguidelinesdocumentedinBWRVIP-07andBWRVIP-63,EPRIReportTR-File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999113170,"ShroudVerticalWeldInspectionandEvaluationGuidelines".ScopeofExamination-AsstatedintheUSNRCSER,NMPCcommitmentwastosubmitthescopeoftheexaminationsforRFO-16totheUSNRC,three(3)monthspriortothestartoftheoutage.6.1.5GenericLetter98-05,BoilingWaterReactorLicenseesUseoftheBWRVIP-05ReporttoRequestReliefFromAugmentedExaminationRequirementsonReactorVesselShellWelds.InNMPCletterNMP1L1391,datedDecember10,1998,reliefwasrequestedpursuanttoGL98-05.NiagaraMohawkPowerCorporation(NMPC)requestedrelieffromtheinserviceinspectionrequirementsof10CFR50.55(g)forvolumetricexaminationofcircumferentialreactorpressurevessel(RPV)welds(ASMECodeSectionXI,TableIWB-2500-1,CategoryB-A,Item1.11,Circumferentialwelds).ThisreliefrequestalsoincludesanalternativetotherequiredinspectionsforRPVshellweldsspecifiedin10CFR50.55a(g)(6)(ii)(A)(2).Additionally,NMPCrequestedapprovalofanalternativetotheexaminationrequirementsspecifiedin10CFR50.55a(g)forvolumetricexaminationoflongitudinalRPVshellweldsandtheshell-to-flangeweld(ASMECodeSectionXI,TableIWB-2500-1,CategoryB-A,Item1.12,andItem1.30).NMPCproposestoperformanautomatedinspectionofcertainRPVweldsusingpersonnelandproceduresqualifiedtothePerformanceDemonstrationInitiative,(PDI).Theuseoftheseinspectionproceduresisaalternativeto10CFR50.55a(b)(2).NMPChasincorporatedtheinformationinBWRVIP-05intothesealternativerequirementsandaddressedtheUSNRCpositionsintheUSNRC'sJuly28,1998safetyevaluationreport.SeeNMPCletterNMP1L1391forspecificdetails.ScopeofExamination-NMP1isreceivedafinalSafetyEvaluationReportfromtheUSNRC.SeeExaminationCategoryB-A,Section2ofthisprogramplanforadditionalinformation.6.1.6NUREG0619-BWRFeedwaterandControlRodDriveReturnLine(CRDRL)NozzleCracking,GenericLetter81-11andGENE-523-A71-0594USNRCGenericLetter81-11forwardedNUREG0619andcorrectedafootnoteintheguide.Thisregulatoryguidedescribesthetechnicalissuesassociatedwiththediscoveryofcrackinginfeedwaternozzlesandcontrolroddrivereturnlinenozzles.TheNUREGalsodescribestechnicalstudiesandanalysisperformedbytheGeneralElectricCompanyandtheUSNRCstaff,thestaff'stechnicalpositionsbasedonthesestudies,andthestaff'srequirementsforlicenseeimplementationofthetechnicalpositions.NMP1initialresponse,datedDecember29,1980,committedtoaprogramofperiodicultrasonicexaminationseveryotherrefuelingoutage,visualinspectionsoftheFeedwaterspargerseveryfourthrefuelingoutage,andliquidpenetrantexaminationseverysixthrefuelingoutageorevery90startup/shutdowncycles,whicheveroccursfirst.SubsequentresponsesamendedtheexaminationmethodsandincludedtheuseoftheGeneralElectricNuclearEnergy(GE-NE)GERIS2000automatedSystem(UT)inplaceofperformingdyepenetrantexaminations.TheUSNRC,intheirletterdatedFebruary5,1999,acceptedtheexaminationprogramsubmittedintheNMPClatestsubmittal,datedSeptember4,1998.ThissubmittalidentifiestheNMP1commitmentsforthethirdinserviceinspectioninterval,andsummarizedasfollows:File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003hIVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TheUSNRC,inaletterdatedJune5,1998,forwardedthesafetyevaluationthataccepted,withmodifications,theBoilingWaterReactorOwnersGroup(BWROG)reportGE-NE-523-A71-0594,"AlternateBWRFeedwaterNozzleInspectionRequirements."Subsequently,intheSeptember4,1998NMPCletter,NMPCreviseditscommitmentforNMP1'sfeedwater(FW)andcontrolroddrivereturnline(CRDRL)nozzleinspections.TherevisedcommitmentfortheFWnozzleinspectionswouldbeinaccordancewiththeBWROGreportGE-NE-523-A71-0594,datedOctober1,1995,subjecttothemodificationsintherelatedUSNRCsafetyevaluationreportdatedJune5,1998.AlsointheSeptember4,1998letterNMPCreviseditscommitmentforCRDRLnozzleinspectionsbyreplacingperiodicliquidpenetrant(PT)withlessfrequentultrasonictesting(UT).TheexaminationtechniqueswillbeinaccordancewiththerequirementsofASMECodeusingtheGEGERIS-2000systemtoperformcontactpulse-echoUTexaminations.TheGERIS-2000systeminspectionisperformedwithsensitivityfordetectingflawsthatismoresensitivethanASMECoderequirements.TheserevisedinspectionswereacceptedbytheUSNRCintheFebruary5,1999letter.FwThefollowingisthelistofmodificationsintheUSNRCsafetyevaluationreport,Section5.0,whichmodifytherequirementsintheBWROGreport:1.TheUTtechniquesshouldhavetheabilitytoreliablydetectaxiallyorientedflawsfromadepthequalto0.25inchesforeachoftheZones1through3andaxiallyandradiallyorientedflawsintheareaofthenozzle-to-safeendweldslocatedinZone5(Figure1).Thenozzle-to-safeendbuttweldinZone5isrequiredtobeinspectedaccordingtoparagraphIWB2500-1oftheASMECode.ThePTmaybeeliminatedfromFWnozzleexaminations,providedthattheUTtechniquessatisfytherequirementsofthe1986orlaterapprovededitionsofASMECodeortheobjectivesofAppendixVill.UTtechniquesthatdonotsatisfythe1986orlaterapprovededitionsofASMECodeortheobjectivesofAppendixVillshallfollowthePTfrequencyshowninTable1.3.TheautomatedUT(gatedpeakthresholdrecording)multiplicationfactorsshallbethoseshownformanualUTinTable2,Method1.AutomatedUT(gatedpeakthresholdrecording)techniquesqualifiedaccordingtotheobjectivesofAppendixVillmayusemultiplicationfactorsinTable2,Methods2or3.4.TheautomatedUT(nothresholdrecording)multiplicationfactorsinTable2,Method3areadequate,providedthattheUTtechniquesarequalifiedaccordingtotheobjectivesofAppendixVill.5.TheinspectionofZone3shallbeatthesamefrequencyasZones1and2,exceptthatlicenseesusingtriplesleevewithdoublepistonringdesignspargermayfollowtheproposedinspectionfrequencyforZone3,butnotlessthanoneinspectioneveryASMECodeinterval.ThefracturemechanicsanalysisshallberecalculatedusingthemorerecentfatiguecurvesintheASMECodethataddressenvironmentaleffects.Theexaminationrequirementsandfrequencyforthethirdinspectionintervalwillbedeterminedbasedontheresultsofthisrecalculation.File:NMP1PP6.WPD

hITNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999(4)Visualinspectionofflowholesandweldsinspargerarmsandspargertees.TheserequirementsarethesameasthosespecifiedinNUREG-0619.ScopeofExamination-ThezonestobeexaminedbytheultrasonictechniquesshallbetheregionsasshownforidentificationpurposesinFigure6-9.Table6-10AUGMENTEDFEEDWATERNOZZLEEXAMINATIONNozzleN4-A31-WD-030-IR31-WD-0301and23AutomatedUTTechniquesFeedwaterNozzleidentificationZoneNoExaminationMethodExtentandFrequency3"PeriodsNozzleN4-B31-WD-021-IR31-WD-021NozzleN4-C31-WD-051-IR31-WD-051NozzleN4-D31-WD-060-IR31-WD-060RV-05-IFeedwaterSpargerAssembliesandFeedwaterNozzlesCRDNozzleN944.1-WD-018-IR1and231and231and23N/AN/AAutomatedUTTechniquesAutomatedUTTechniquesAutomatedUTTechniquesVisualVT-3ExaminationAutomatedUTTechniques3"Periods3"Periods3RePeriodsEvery4Ž.RefuelingOutage,commencingatRFO-8,(1981),Scheduled3"Period3"PeriodFile:NMP1PP6.WPD

VNIAGARAUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999VcssclSafe-EndNozzleMAt%3282AFigure6-9FEEDWATERNOZZLEZONESFilo:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003ElYNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19996.1.7NUREG-0803/GenericLetter81-34and86-01-BWRScramSystemPipeBreakGenericLetter81-34transmittedNUREG-0803toallBWRlicensees.NUREG-0803,"GenericSERRegardingIntegrityofBWRScramSystemPiping",addressestheneedforimprovementinprocedures,periodicinserviceinspectionandsurveillanceforthescramdischargevolume(SDV)system.TheseguidelinesweredevelopedtoaddresstheconsequencesofapostulatedleakagecrackintheSDVpipingandtheresultinglargeleakage(upto550gpm)downstreamofthesystemisolationvalves.GenericLetter86-01,"SafetyConcernsassociatedwithPipeBreaksintheBWRScramSystem",addressedthestaff'spositionbasedoninformationprovidedinBWROGandGeneralElectricCompanysuppliedgenericinformation(NEDO-22209,BWROG-8420)andstaffgenericanalysisoftheSDVpipingsystemintegrity.ThestaffhasconcludedthatSDVpipingsatisfiesBTPMEB3-1,positionB.2.C(1).Athroughwallleakneednotbepostulated.AlsoBWROGemergencyprocedureguidelinesandvisualverificationoftheSDVintegrityprovidesufficientmeasurestoverifythedetectingandmitigatingtheconsequencesofleakage.ScopeofExaminations-BasedontheaboveinformationNMP1willperformtheexaminationsandtestsrequiredbythe1989EditionofSectionXIforClass2systems.Noadditionalaugmentedexaminationisrequired.6.2IndustryDocuments6.2.1In-VesselVisualExaminations(BWRVIP)InadditiontotheASMECoderequirements,thissectionidentifiesthoseadditionalexaminationactivitiesthatNMPChasevaluatedanddeterminedtobeapplicabletotheThirdInspectionInterval.Augmentedexaminationsmayberecommendedbyregulatorydocuments,NSSSrecommendations,industryexperience,and/orgoodengineeringpractice.TABLE6-.11,,','.;:';;::,;,',,",",;;,,:,;;:.~~;;,~;.",',:,:,:'.":,':"..INVESSELAUGMENTEDEXAMINATIQNS,=',::.",js":,,",,",'...'."K.';.;.,;,j:.;.,;Compoiient(1}Idet1tlfication",.ExanjInspe,etio'rt;..,!"'.:,~<!,"-,',Method'equirements'Exter'it,&iid'Prequ'e'ncy,;.TopGuideSteamDryerAssemblyVisualVT-3VisualGERICSIL071BWRVIP-26EPRITR-1072851RICSIL059SIL554BWROG91GESIL474Periodicallyasrequired(Note4)Periodicallyinspecttoassesscomponentcondition;UTinspectasnecessarytocharacterizecracking;(Note3)File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003HYNIAGARAaVMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TABLE6,-11.,IN(VESSEL,AUGMENTED'EXAMINATlONS','omponent,(4}'IdentificationCoreShroudAssembly,ShroudRepairComponentsandShroudSupportsCoreSprayandCoreSpraySpargerMoistureSeparator/ShroudHeadsAssemblyShroudHeadBoltsFeedwaterSpargerNozzleIRM/SRMDryTubes(2)Exam...;.Method"'isualVT-3UTEVT-1VisualVisualVisualUTVisualVisual;-.IrispectIon:',.Requirements.BWRVIP-07(EPRITR-105747)BWRVIP-01,BWRVIP-38,BWRVIP-63NUREG/CR4523BWRVIP-18EPRITR-106740BWROG91GESIL433GoodEngineeringPracticeSil-433GoodEngineeringPracticeBWRVIP-47SIL409Rev.1RICSIL073Extentand'FrequencyExamineShroudTieRodAssembliesperdetailsinNER-1M-053;ShroudVerticalwelds,shroudsupportweldsH88H9,andshroudComponentWelds(Note4)ExamineCSPipingandCSSpargerAssemblyandpipingcomponentcondition(Note4),Periodicallyinspecttoassesscomponentcondition(Note3)Periodicallyasrequired(Note3)Visuallyinspecteachfourthrefuelingoutage,ExaminethenozzlesonthereplacementFWSpargeronaperiodicbasis(Note3)Examineonaperiodicbasistoassesstheconditionsofthetubes(Note3,4)ControlRodDriveStubTube/HousingPenetrationsIn-CoreInstrumentation/HousingPenetrationsCoreDeltaPressure/StandbyLiquidPoisonControlCorePlateVisualVisualVisualVisualBWRVIP-47GoodEngineeringPracticeGoodEngineeringPracticeBWRVIP-27GoodEngineeringPracticeGERICSIL071BWRVIP-25EPRITR-107284SIL588WhenAccessible(Note3,4)WhenAccessible(Note3)WhenAccessible(Note3,4)Periodicallyasrequired(Note4)Fife:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI>>003LIVNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999..."...,"'"':::.':;:"':".:.-...TABLE6-"I'.I';'.::,,:;",;.;:,.,;.':.,;;,';...;,.'iN;VESSEL"'AuGMENTEDEXAMINATIONS;;.,'...Component:(1)identification>>".>>':."ExamMethodInspection:;'-'.;-:-.;:".,RequIremerit>>sExtentandFrequency,ControlRodDriveReturnLineNozzleVisualNUREG0619InspecteachoutageuntilfinalPTisperformed.NMPCLetterNotes:(1)(2)(3)(4)NMPChasnotdeterminedwhetherreexaminationofalltheseareas,(asdefinedabove)iswarrantedduringtheThirdInserviceInspectionInterval.IRM/SRMDryTubeshaveallbeenreplacedin1986withthree(3)differenttypedesignsandtwomanufacturerswithType347material.Theseinspectionsarenotcommitmentsandaresubjecttochangeasnecessarytosupportgoodengineeringpractices.TheseinspectionswillbebasedonapprovedBWRVIPguidelinesfortheidentifiedcomponents.6.2.2SIL571-instrumentNozzleSafeEndCrackingandBWRVIPs-06(TR-1507),VIP-27(TR-107286),VIP-49(TR-108695)SIL571,InstrumentNozzleSafeEndCracking,identifiedaleakinareactorvesselwaterlevelinstrumentnozzlesafeendataGEBWR/4plantanddocumentstheresultsofinvestigationsandexaminationsthatwereperformed.SubsequentlytheissuehasreceivedsubstantialindustryexposureincludinginvestigationsandreviewsaspartoftheBWRVesselandInternalsProject(BWRVIP)work.NMPChasevaluatedthisconcerninDeviation/EventReportff1-93-2209.ThefollowingexaminationswereestablishedfortheinstrumentnozzlesandtheStandbyLiquidControl(SLC)nozzle.PerformaVT-2examinationaftervesselflooduptoassessforthepresenceofleakageatthestartofeachrefueloutageand,FollowupwithaVT-2examinationattheendofeachrefueloutageduringthesystempressuretest.TheNMP1designincludeseleven(11)nozzleswithstainlesssteelsafeends,ten(10)instrumentnozzlesandone(1)standbyliquidcontrolnozzle.Thesenozzlesareidentifiedbelow.4Table6-'12.',InstrumentNozzies-StainlessSteelSafeEndsN12N13AN13BN14AN14BN15AN15BN16AN16BN17A'Safe;End.'-'MaterialSA336-F8SA336-F8SA336-F8SA336-F8SA336-F8SA336-F8SA336-F8SA336-F8SA336-F8SA336-F8'levation266'1"306'0"295'1"305'0"295'1"305'0"295'1"306'0"295'1"311'2"'-Azimuthderees'8576282236236244244250'escriptionStandbLiuidControlInstr.LevelProtectionInstr.LevelProtectionInstr.LevelControlRaneInstr.LevelControlRaneInstr.LevelControlRaneInstr.LevelControlRaneInstr.LevelProtectionInstr.LevelProtectionInstr.WideRaneLevelFile:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003ElTNIAGARAa&MOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999-::.>:Table6-12.InstrumentNoiztes-StainlessSteelSate:Ends'Nozzle'ff=-"";:.-'.Safe:End',-,.Elev'ation:Azimuth',~.'":;"""'.".';"',;';::,'",.::Mate'r'Ial",""".:.'.~~"."".""."de'"rees,',Descrlptlon::-;N178SA336-F8295'1"252Instr.WideRaneLevelAllofthereactorinstrumentnozzlesafeendsandthestandbyliquidcontrolsafeendarefabricatedofstainlesssteelmaterialSA-336F8Three(3)safeendtonozzleweldsarescheduledforexaminationasfollows:Table6-13>,','.'-.';-'-"";:-"'~.i".InstrumentIItozzles-CodeExamina'lions~Nozzle':.:.',t';)804'."'.'."ExamID::--:,,':"-,'CodeCategory/item"~:;:~~;;...:ExamExam.ScheduleN12N13AN16A148C42.1-WD-03436-WD-00336-WD-9248-F/85.208-F/85.208-F/85.20SurfaceSurfaceSurface1eriod3'flcd3'riodOnlythecoderequiredexamsarescheduledfortheabovewelds.Theexaminationisperformedusingliquidpenetrantandincludestheadjacenth"portionofthebasematerialoneachsideoftheweldment.Shouldtheexaminationrevealindications,Engineeringshalldeterminethenecessityforexpansion.AdditionallytheremainingnozzlesreceiveaVT-2examinationeachrefueloutageduringsystempressuretest.StandbyLiquidControlNozzleDuetotheimportanceoftheSLCnozzletheBWRVIP-027Guidelinesrecommendavolumetricexaminationbeperformedonthenozzletosafeendweldandthesafeendextension.NMPChasevaluatedthisrecommendationinDeviation/EventReportff1-97-0378.Thefollowingsupplementalexaminationhasbeenincorporatedinthisplan.""Table,6-14"'->>~-:'"'-""':.":InstrumentNoiztes"-Stan'db"LIuid'CohtrolISO:";'Exam,ID.',",'Code,",."'".'-'.:.,',.;,"Examination'.Examination-Cateo/Item':-~Method~"ScheduleN1242.1-WD-0348-F/85.20Volumetric3'4PeriodThevolumetricexaminationincludestheweldbetweenthenozzle(Alloy600material)andthesafeend(StainlessSteel)andtheaccessiblelengthofthesafeendbasemetal.TheseexaminationswillbeperformedusingASMESectionXImethodologyandcriteriatotheextentpractical.Ifindicationsarelocated,flawsizingshallbeperformedinaccordancewithSectionXIrequirementsandreportedtoEngineering.SincetheRPVinstrumentnozzlesarefabricatedinthesamemanner,Engineeringwillalsodeterminethenecessitytoexpandthescopetotheinstrumentnozzles.File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003NTNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19996.2.3SIL409andRICSIL073,IncoreDryTubeCracksSIL409andSIL409,Rev.1,IncoreDryTubeCracksfoundinincoredrytubesatthreeoperatingBWR'sandtoalertBWRownerstotheneedforinspections.Recommendedactionwastoinspectthedrytubsduringthenextrefuelingoutage.NMPCperformedvisualexaminationson12drytubesin1984usinganunderwaterTVcamera.Thedrytubeswerecrackedbutstillserviceable.Thedrytubeswerereplacedin1986(RFO-10).Thenewdrytubesarethreedifferenttypedesignandtwomanufacturers,KraftworkUnion(KWU)andGeneralElectric(GE).TherearetwonewstyleKWUdesign,eightnewstyleGEdesign,andtwooldstyleGEdesign.ThenewKWUdesignismadeofahigherstrengthmaterial,(347stainlesssteel).ThenewstyleGEdesignhasahigherpurity,betterqualitystainlessintheareawherethecrackinghadoccurred.Bothdesignsarecrevicefree.In1988,bothoftheoldstyleGEandoneeachofthenewdesignswereexamined.Noindicationswerefound.TheseexaminationswererepeatedduringRFO-06andnoindicationswerefound.RICSIL073,datedMay12,1995,presentedadditionalinformationonrecentcrackinginincoredrytubes.ScopeofExaminations-ConductvisualexaminationoftwooldstyleGEdesign,everyotherevennumberedoutage.ComponentIdentificationTable6-'I5IRMIncoreDryTubeAssemblyComponentDescriptionOutageSelectionSIL409-IDTC1245SIL409-IDTC3645IRMIncoreDryTubeAssemblyIRMIncoreDryTubeAssemblyRFO-16RFO-18RFO-16RFO-186.2.4SIL419,CRDHydraulicControlUnitIsolationValvesInaccordancewiththerecommendationofSIL419,theCRD101and102valvewedgesareexaminedwithliquidpenetrantwhentheircompanionCRDisremovedformaintenance,toamaximumoffive(5)CRD'sperrefueling.ScopeofExamination-Noexamsrequired,allvalvesreplacedand/orupgraded.6.2.5SIL433,ShroudHeadBoltCracksSIL433andSIL433,Supplement1,identifiedcrackingofheadboltsinfourBWR/4'sandoneBWR/3.RecommendationswereultrasonicexaminationsofallBWR/2-5'sheadboltsthenexttimethereactorvesselheadisremovedandtheshroudheadandseparatorassemblyisremovedtotheequipmentstoragepool.AdditionalinformationwaspresentedinSIL433Supplement1,datedSeptember15,1993thatrevisedthe.recommendations.ThecauseofcrackingwasconfirmedtobecrevicecorrosionIGSCCandrecommendedtheentirelengthoftheheadboltsbeexamined.DuringRFO-10,NMP1examinedall36boltsandnoindicationswereidentified.TheseexaminationswererepeatedduringRFO-11andnoindicationswereidentified.Examinationswillberepeateduntilanevaluationsupportstheirdeletion.SeeNMPCletterNMP-36220.File:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999ScopeofExamination-Examinationsaretobeidentifiedlater.6.2.6SIL455andRICSIL072,RecommendationforAdditionalISIofAlloy182NozzleWeldmentsSIL455identifiedIGSCCtypeindicationsinoneoften-recirculationinletsafe-endtonozzleInconel182weldments.Oneoftheaxialcomponentshadextendedaboutonequarterinchintothealloysteelmaterialandhasbeenrepairedbytemperbeadweldoverlay.TheSILrecommendedBWRownersperformadditionalultrasonicexaminations,duringplannedinserviceexaminations,ofsafe-endtonozzleweldmentsifcracksarefoundinalloy182.SubsequentlyRevision1,andRevision1Supplement1hasbeenissued.TheserevisionsrecommendownersreviewtheirdesignfortheforRecirculationinletandoutletnozzles,highpressurecorespray,lowpressurecoresprayandlowpressurecoolantinjectionnozzles,Jetpumpinstrumentationnozzles,andcontrolroddrivehydraulicreturnnozzles.Forthosedesignswherealloy182extendsbackintothenozzlebore,UTexaminationsshouldbeperformedinthisextendedarea.AlsoGErecommendsthata45-degreeanda60degreerefractedlongitudinalwavebeusedforcrackdetectionandsizing.ATNMP134nozzlesutilizedesignsinwhichInconelweldbutterextendsbackintothenozzlebore.SeeNMPCletterMNP36220.AdditionalinformationwaspresentedinRICSIL072,datedJanuary10,1995.Table6-16..'::,:,SIL466SelectedNeids-..."Compon'ant:fderttifIcatl~oit'"".'"-',~'-",'"'Coiiip'orIeiitDisci)ptfon"""'"-,"Exam"MethodWhart"..SelectedRV-WD-011RV-WD-013RV-WD-015RV-WD-017RV-WD-019RV-WD-021RV-WD-023RV-WD-025RV-WD-027RV-WD-029RV-WD-031RV-WD-033RV-WD-035NozzleN7A-FlangeNozzleN7B-FlangeNozzleN7C-FlangeNozzleN8D-FlangeNozzleN7E-FlangeNozzleN7F-FlangeNozzleN7G-FlangeNozzleN7H-FlangeNozzleN7J-FlangeNozzleN7K-FlangeNozzleN7M-FlangeNozzleN7N-FlangeNozzleN7P-FlangeUTUTUTUTUTUTUTUTUTUTUTUTUT1e'eriod3"Period3~Period3"Period1"Period3"Period3"ePeriod3RoPeriodPeriod1~Period1eTPeriod3Period3"ePeriodFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARAVMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999ComponentIdentificationRV-WD-037RV-WD-039RV-WD-041RV-WD-04332-WD-04232-WD-08232-WD-12232-WD-16432-WD-20832-WD-00232-WD-04532-WD-08532-WD-12532-WD-16736-WD-107437-WD-00239-WD-00239-WD-09040-WD-03940-WD-08044.1-WD-017Table6-16SINGSSelected%aidsComponentDescriptionNozzleN7R-FlangeNozzleN7S-FlangeNozzleN7T-FlangeNozzleN7U-FlangeN2ANozzle-SafeEndN2BSafeEnd-NozzleN2CSafeEnd-NozzleN2DSafeEnd-NozzleN2ESafeEnd-NozzleN1ANozzle-SafeEndN1BNozzle-SafeEndN1CNozzle-SafeEndN1DNozzle-SafeEndN1ENozzle-SafeEndN7LClosureHeadN8Nozzle-FlangeN5ANozzle-SafeEndN5BNozzle-SafeEndN6ANozzle-SafeEndN6BNozzle-SafeEndN9SafeEnd-NozzleExamMethodUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTWhenSelected3"0Period3"ePeriod1sTPeriod1Peripd2"ePeriod3"ePeriod1s'eriod2"Peripd3"ePerjpd2"Period3RoPeriodpeljpd3"Period1Period3RDPerjpd2'ePeriod1Peripd3"Period1"Period1Period1s'eriod6.2.7SIL474,SteamDryerDrainChannelCrackingScopeofExamination-AsrecommendedbySIL474,SteamDryerDrainChannelCracking,NMP1willvisuallyexaminesteamdryerdrainchannelseachperiod.File:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnlt1NMP1-ISI-003ElYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999.~~~X+,,~~ca'Component'Identification;>'..RV-01-I.','Table,6'-".'l7;;:."',:."....SIL474Stear'n,Dryer'.Component0'esc'rlptionSteamDryerDrainExam'.-MethodVT-1':.FrequencjOnceeveryperiod6.2.8SIL483,CRDCapScrewCrackIndicationsSIL483,CRDCapScrewIndications,identifycircumferentialcrackingandcorrosionpittingintheshankdirectlybelowthecapscrewhead.SIL-483.Rev.2recommendsvisualexaminationofallremovedcapscrewsforcrackindicationsintheshank-to-headtransitionregionwhenevercapscrewsareremovedforroutinemaintenance.ThisSILresultedfromexaminationsperformedbyNMP1.AnanalysisoftheseexaminationresultswasissuedbyGEinMarch17,1989.ThisSILrelaxespreviousNMP1commitments.ScopeofExaminations-AnLPexaminationwillonlybeperformedonsuspectcapscrewsslatedforreuse.Noexaminationsarescheduledpursuanttothisplan.6.2.9SIL539,RPVHeadCladCrackingSIL539,RPVHeadCladCracking,identifiescrackinginthestainlesssteelcladdingoftheRPVtophead.Thecrackingwasidentifiedbyvisualexaminationthatrevealedruststreaksonthecladdingsurface.VisualexaminationswillbeperCodewithparticularattentiongiventobackcladareasoftheflangetodomeweld.Ifindicationsarefound,aconfirmatoryliquidpenetrantexaminationorenhancedultrasonictestingisperformed.AlsoseeUSNRCInformationnoticeNo.90-29.ScopeofExamination-Noexaminationsareplannedduringthisinterval.Table;6.,:,~1'8,:'RPVHead;Cladding.::ComponentIdentification'-.',"-=.',,-'omponent.'.-.-.';;.-'".'Exam,Description,':,-;;-',-'.';:.,Method,,'2RV-16-IVesselCladdingVT-3NoExamsPlanned6.2.10SIL554,TopGuideCrackingSIL554,TopGuideCracking,identifiedathroughwallcrackapproximately1and~AincheslonginatopguideofaBWR/2.ThisSILrecommendsownersofBWR/2,3,4and5plants,withtopguidefluencelevelsabove1x10"neutronspersquarecentimeter,performvisualinspectionsofthetopguideatgridlocationswherefuelandbladeguideshavebeenremoved.Whenevercrackingisfound,performanultrasonicexaminationofthebeamtopguideintersection.NMP1performedtherecommendedvisualexaminationsinRFO-12andnocrackingwasfound.File:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003alTNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999ScopeofExamination-ExamineperBWRVIP-26recommendations.',',Tabfe'6-'19,,,~Upper-,'Cori.Grid';,Compor'meritIderitlfication.'omponent'.:,;;.,.:Descrlptfori"'"'"::,=::ExamMethodFrequency,RV-13-IUpperCoreGridLaterPerBWRVIP-266.2.11SIL588,TopGuideandCorePlateCrackingSIL588,TopGuideandCorePlateCracking,identifiedthatinspectionsshowedsignificantcrackinginthecoreshroud,topguideandcoreplaterims.Theitemsweremanufacturedfromtype347stainlesssteel,whichisaniobiumstabilizedausteniticstainlesssteel.GEconsiderswelded347SStohavesusceptibilitytoIGSCC.TheSILrecommendsavisualexaminationatthenextrefuelingoutage.NMP1hasdocumentedtheevaluationofthisSILinDeviationReport/EventReportDER¹1-95-0436.ScopeofExaminations-VisualexaminationswillbeperformedaspartoftheSectionXIexaminations,CategoryB-N-2,itemB13.40.AugmentedexaminationswillbeperformedperBWRVIP-26..Table6-,20.SIL-'SSSUpper,Core',GridComporient.fde'ritlffcatiort,::.'Component,;-::;;.-:,',',""-'"'Desclptln':"".""""'""'MQp'Exam',.:.,Frequency',:,',';,RV-13-IUpperCoreGridLaterPerBWRVIP-266.2.12SIL459,RecirculationPumpShaftCrackingSIL459,supplement2,wasissuedtoinformGEBWRownersofshaftcrackinginrecirculationpumpsmanufacturedbyByronJackson(BJ)andbyBingham.BJmanufacturedtherecirculationpumpsatNMP1.Supplement2,oftheSILprovidedadditionalinformationformthatpresentedinSIL459,Rev.0andSIL459,Supplement1.Thecombinedinformationissummarizedbelow.ThereisaSIL459,Supplement3;however,itisnotapplicabletoNMP1.SIL459wasissuedinDecember1987andidentifiedthefirstinstanceofthermalfatiguecrackinginBWRreactorrecirculationpumpshafts.TherecommendedactionwastoperformNDEontheshaftswhenthepumpisdisassembled.ForadditionalinformationseeNMPCletterNMP31096,QA91-U1-080,NMP34194andNMP45971.File:NMP1PP6.WPD

YNIAGARAVMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999InSIL459,Supplement1,therewasnochangeintherecommendationtoperformNDEonthepumpshafts.ForadditionalinformationseeNMPCletterQA91-U1-281.Thisletterindicatesthat3ofthe5shaftshavebeenexaminedandtheremaining2willbeexamined.InSIL459,Supplement2,providedadditionalinformationaboutpumpswithheatexchangersandadiscussiononshaftvibration.TherewasnochangeintherecommendationtoperformNDEonthepumpshaftswhendisassembled.ScopeofExaminations-NDEexaminationofthepumpshaftswhendisassembledformaintenancehasbeenincludedinthisinspectioninterval.TaMe6-21SIL-459PumpShaftsComponentIdentlficatlon32-187-Shaft32-188-Shaft32-189-Shaft32-190-Shaft32-191-ShaftComponentDescrfptlonPump11ShaftPump12ShaftPump13ShaftPump14-ShaftPump15-ShaftExamMethodVT-1VT-1VT-1VT-1FrequencyWhendisassembledWhendisassembledWhendisassembledWhendisassembledWhendisassembled6.2.13IEBulletin80-13SIL289andRISIL073,CrackinginCoreSpraySpargersIEBulletin80-13,CrackinginCoreSpraySpargers,identifiedthatOysterCreekandPilgrimhadfoundcracksintheircoresprayspargers.BothOysterCreekandPilgrimhadperformedtheirexaminationsinaccordancewiththerecommendationsinGESIL289.SubsequentlyexaminationswereperformedbyNMP1onfour(4)coresprayspargersandassociatedinternalpipingsegment(thesectionofpipingbetweentheinletnozzleandthevesselshroud)usingaremoteunderwatertelevisioncamera.IndicationsidentifiedonLoopACoreSpraySpargerpipenearSprayNozzle23AduringRFO-13wereevaluatedandsubmittedtotheUSNRConApril21,1995.Theindicationswereevaluatedbyfracturemechanicsandthespargerwillnotbepreventedfromperformingitsfunction.Norepairsarenecessary.NMP1willcontinuetoperformexaminationsateachrefuelingoutageandanypropagationofindicationswillbeevaluated.SIL289,Rev1,Supplement1,Revision1,issuedMarch15,1989identifiedadditionalcrackinginthecorespraysparger.SubsequentlyRISIL074,datedNovember1,1995wasissuedwithadditionalinformation.ScopeofExamination-ExaminationswillbeinaccordancewithBWRVIP-18.File:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNIAGARAklMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999Comporient:IdentNcatlonpray,Sparger...Frequency...CommentsCompoiient".'"Description"."-',Exam,Method;:,:-'..:;...;;Table'6<<',22':~~.'"~~';;;"-:::'.RV-06-IRV-07-ICoreSpraySpargerCoreSprayLinesVT-3VT-1EachOutageExamineperBWRVIP-18.EachOutageExaminePerBWRVIP-186.2.14IEBulletin96-03,PotentialPluggingofEmergencyCoreCoolingSuctionStrainersByDebrisinBoilingWaterReactorsInNMPCletterNMP1L1151,dated11/4/98,NMP1committedtoperforminganaugmentedvisualexaminationofthecorespraysuctionstrainersinaccordancewiththerecommendationsofIEBulletin96-03.ScopeofExamination-Performvisualexaminationseachrefuelingoutage..:-;".i;::-:,",';,";,~P,IEB.96-03.SuctionStralriersCom'ponent-ldentlflcatlon,'-:-'Component,.'.'::Exa'rn-,'".",-:'Descrlption"-'-:.".Method;Frequency80-0980-3080-1080-3981-0581-0681-2481-25Ctmt.SprayCtmt.SprayCtmt.SprayCtmt.SprayCoreSprayCoreSprayCoreSprayCoreSprayVT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3EachoutageEachoutageEachoutageEachoutageEachoutageEachoutageEachoutageEachoutageFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElVNIAGARAaUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,19996.3AdditionalCommitments6.3.1NCTSCommitmentNo.503783-01,AugmentedExaminationsofCRDHousingIn1984NMP1identifiedadegradedmaterialconditiontoControlRodDrive(CRD)stubtubes.TheconditionwasinitiallyevaluatedbytheUSNRCinJune1984andthattheRollRepairmethodusedwasacceptable.Thismethodlimitedleakagefromthepenetrationsandassuredsafeoperationofthefacility.TheUSNRC'ssafetyevaluationwassupplementedbyUSNRCSafetyEvaluationdatedMarch25,1987.SubsequentlyUSNRCcorrespondencedatedAugust9,1993requestedthatNMP1developanaugmentedinspectionprogramforperiodicexaminationofthecriticalareasoftheCRDhousings.SpecificallythestubtubeupperJweldsandthepreviouslyrolledrepairedregions.Thehousingsthathavenotbeenrepairedareincludedintheprogram.ScopeofExamination-Theaugmentedprogramincludesultrasonicexaminationoftheupper-Jweldandtheroll-repairedareasoftheCRDhousingspriortoandaftereachrollrepair.TheUTexamincludestheupper-Jweldplusaminimumof1"aboveandbelowtheupper-Jweldtoaccountfortheheataffectedzone(HAZ).TheUTexamoftherolledareaofthehousingshallincludethevolumeofbasematerialassociatedwiththeroll;andtoaccountfortherolledtounrolledtransitionareas,willextendatleast1"aboveandbelowtherollband.Eachrefuelingoutageaminimumoftwo(2)previouslyroll-repairedCRDhousingswillrequireaUTexamandonly,ifpreviouslyroll-repairedCRDhousingsaremadeavailablethroughnormaldrivemaintenance.Thehousingswillbeselectedfromthosethataredisassembledformaintenance.EngineeringDesignDrawingD6340-100-163shallbeupdatedasrequired.InadditionboltingwillreceiveaVT-1onhousingsthataredisassembled.AllhousingsandCRDpenetrationswillreceiveaVT-2examforevidienceofleakageduringthesystempressuretestconductedeachrefuelingoutageandthemid-cycleshutdownwhendrywellisde-inerted.:;;,'~;-::,",;..:.CRDH:Upper"=;-J:,Weld'andRoll"Area'Ltstinj"::;:.',Component:-.;"::::.:;...:;;-":g;":.,';,;;:,Comjonent,-:=':.':,.'.",';,Identlflcation'::,',::,"":,':."'.":."'~";-,:,,Qescriptfon':;--"~",.".Exam,MethodFrequency:,.:.-,DRV-44-0219(NC02)DRV-44-0631(NC02)DRV-44-1015(NC02)CRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaUTBolting-VT-1UTBolting-VT-1UTBolting-VT-1Whendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageFile:NMP1PP6.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003ElYNlAGARAaUMOHAwKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999'"'--':4"--abie6'-24"""""':""">>"'-"':.;",-.'-CRDHUpper;JVfefdandRoII.Area,LIstiiig;.'-Component""':"CompotierifIdentification...Description,ExamMeth'od'requencyDRV-44-1027(NC02)DRV-44-1411(NC02)DRV-44-1803(NC02)DRV-44-1819(NC02)DRV-44-2251(NC02)DRV-44-2647(NC02)DRV-44-3007(NC02)DRV-44-3047(NC02)DRV-44-3051(NC02)DRV-44-3407(NC02)DRV-44-3415(NC02)CRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaUTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1Whendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageFile:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnlt1NMP1-ISI-003VNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999'.-'::.'"':-'-"':-"=-:.-:;-::.-;;"-':-'"'CRDHUpper-JNefd'and:;Ro'II,'Area'Listfn'9Ideittfffcstlon,'"-'",,-',',;"'"":,.';:DRV-44-3419(NC02)DRV-44-3431(NC02)DRV-44-3439(NC02)DRY-44-3451(NC02)DRV-44-3811(NC02)IDRV-44-3831(NC02)DRV-44-4227(NC02)DRV-44-4239(NC02)DRY-44-4627(NC02)DRY-44-4639(NC02)DRV-44-5019(NC02):,Compon'ent'DescriptionCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaExam':Meth'odUTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1FfeqUeACQ,Whendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageFile:NMP1PP6.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003VNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999;.CRDHUpjii'.;;"O',VteidandRiffAreaUsting'--;.:";.'::;.:>>"7,Com'ponent"-:IdentiffcatloriComponent',"=',"'.'*"escrlptiaraExamMethodFreju'en'RV-44-4219(NC02)DRV-44-5023(NC02)DRV-44-4231(NC02)DRV-44-3403(NC02)DRV-44-0223(NC02)DRV-44-0235(NC02)DRV-44-5035(NC02)NCTS503783-1AIISRDHCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHUpper-JWeldandRollAreaCRDHExteriorIRxBottomHeadUTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1UTBolting-VT-1VT-2Whendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageWhendisassembledformaintenance(2)DRHousingseachOutageAllCRDHousings,CRDPens.,LeakagerequiredduringeachRFOandMid-cycleshutdownwhendrywellDe-inerted6.3.2INPORecommendationSER5-85,ThermalFatigueCrackingatMixingPointsInaccordancewiththerecommendationsoftheInstituteofNuclearPowerOperations(INPO)SignificantEventReport(SER)5-85themixingpointsofsystemsthatexperiencefluctuationsintemperaturewhichcouldleadtothermalfatiguecrackingshouldbeexaminedeachrefuelingoutage.TheReactorRecirculationSystemhasmixingpointsfortheEmergencyCoolingandShutdownCoolingSystems.Anexaminationofthesethreeareasshallbeperformedduringeachrefuelingoutage.ScopeofExamination-Thebasematerialoftheteebetweenwelds32-WD-004,32-WD-004A,and32-WD-005.Theexaminationshallcover100%ofthebasematerialor12"fromthecenterline,Fife:NMP1PP6.WPD 0

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003VNlAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999whicheverisless.Thebasematerialoftheteebetweenwelds32-WD-170,32-WD-171,and32-WD-172.Theexaminationshallcover100%ofthebasematerialor12"fromthecenterline,whicheverisless.Thebasematerialoftheteebetweenwelds32-WD-203,32-WD-204,and32-WD-205.Theexaminationshallcover100%ofthebasematerialor12"fromthecenterline,whicheverisless.Component-'-";,.identifi~atio~'.-':Tee'ocationTable'8:-,,25TeeBaseMaterial..."Re'ISO'o.-'uehngOutage2"e'Perio'd,.3~Period'2-WD-204-MT32-WD-004A-MT32-WD-171-MT14.0"Discharge15D12.0"Suction11S28.0"Suction15SYesYesYesYesYesYesYesYesYesYesYesYesIfflawsdeeperthanthoseallowedbyASMESectionXI,IWB3514.3arefound,theweldmustbeevaluatedinaccordancewiththecrackevaluationcriteriaidentifiedAttachment2ofUSNRCGenericLetter84-11.File:NMP1PP6.WPD

NYNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTSSECTION7-RELIEFREQUESTSTableofContentsRecordofRevision7.0RELIEFREQUESTS7.1SecondInspectionInterval7.2ThirdInspectionInterval...7.3ReliefRequestContent..7-17-27-37-37-37-3File:NMP1PPT.WPD

ElYNIAGARAIIUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-IS!-003Rev.0Date:September27,1999"4::.~">'>>>>>>~~:"f~<.<<"~'ECORDOF'REVISION.j':0>>~..'"~'AWE.i""~"i"""',~g@jP%'"REVISION',No.':.,-'~DATE'~""FFECTED'-'-PAGES';'""',.:.-'::,:.'-",';.':REASON;FORREVISION"0September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PP7.WPD

hlVN(AGARAa4woHAwKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19997.0RELIEFREQUESTS7.1SecondInspectionIntervalDuringtheSecondTenYearInserviceInspectionInterval,therewerecaseswherecomponentconfigurationand/orinterferencepreventedthecoderequiredvolumeorsurfaceareafrombeingexaminedinit'sentirety.Ineachcasewheresuchlimitationswereencountered,thedetailsweredocumentedonaRequestforReliefandsubmittedtotheUSNRCasrequiredby10CFR50.55a.7.2ThirdInspectionIntervalAdetailedreviewofthepreviouslysubmittedRequestsforReliefwasperformed,andbasedonthatreview,RequestsforReliefonitemswhichremainapplicablefortheThirdInserviceInspectionIntervalareincludedinAppendixFofthisprogram.AppendixFincludesalistingandthestatusofeachRequestforReliefsubmittedtotheUSNRCaspartofthisprogram.Note:Examinationvolumeorsurfaceareathatcannotbeexaminedduetointerferencebyanothercomponentorpartgeometry,areductioninexaminationcoverageonanyweldwillbeconsideredacceptableprovidedthereductionincoverageforthatweldislessthan10%.Subject.ofCodeCaseN-460.ExaminationvolumeorsurfaceareainterferencethatdoesnotmeetthecoveragerequirementsofCodeCaseN-460,willbedocumentedintheformofaReliefRequestper10CFR50.55a(g)(4)(iv).Incaseswherepartsoftherequiredexaminationareascannotbyeffectivelyexaminedbecauseofacombinationofcomponentdesignorcurrentinspectiontechniquelimitations,NMPCwillcontinuetoevaluatethedevelopmentofneworimprovedexaminationtechniqueswiththeintentofapplyingthesetechniqueswhereapracticalimprovementontheexaminationcanbeachieved.7.3ReliefRequestContentEachRequestforReliefwillcontainthefollowinginformation:A.ComponentIdentification-describestheCodeClass,CodeExaminationCategory(ifapplicable)andabriefdescription;B.ExaminationRequirement-describestheCodeItemNumber(s)andtheexaminationrequirements;C.ReliefRequested-providesadescriptionoftherelieffromtherequirementsoftheCodethatcannotbecompliedwith;D.BasisforRelief-describesjustificationtosupportthereasonreliefisbeingrequested;E.AlternativeExamination-describesexamination(s)orteststhatNMPCproposesFile:NMP1PP7.WPD

VNIAGARA4MOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999touseinlieuofthecurrentrequirements;ImplementationSchedule-denotestheinterval,period,and/oroutage(whicheverisapplicable),thatNMPCproposestoimplementtherelief;G.AttachmentstotheRelief-identifyallFigures,Tables,Sketches,Photographs,etc.,attachedtotheRequestforRelief.Allattachmentsshouldbereferencedwithintheapplicabletext.Note:FollowingreceiptoftheUSNRCSafetyEvaluation,aUSNRCResponseSectionmaybeaddedtoeachRelief.File:NMP1PP7.WPD

hlYNIAGARAA@MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContentsRecordofRevisionTABLEOFCONTENTSSECTION8-ACCEPTANCESTANDARDS8-18-38.0ACCEPTANCECRITERIA.8-48.1AcceptancebyExamination8.2AcceptancebyRepair8.3AcceptancebyReplacement8.4AcceptancebyAnalyticalEvaluation..8.4.1Class1Components8.4.2.Class2Components8.4.3ClassMCComponents8.5AcceptancebyEngineeringEvaluation.8.6AcceptancebyCorrection8.7AcceptancebySupplementalExamination8.8AcceptanceCriteriainCourseofPreparation.8.9AdditionalExaminations.8.9.1Class18-48-48-48-48-58-58-58-58-68-78-78-78-78.9.2Class28.9.3Class38.9.4ComponentSupports8.9.5ClassMC8-88-88-98-98.9.6IGSCCSampleExpansion8-10File:NMP1PPB.WPD

ElVNIAGARAH4MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTS-Continued8.10DefectsFoundOutsideSectionXIExamination8-10LISTOFTABLESTable8-1Class1AcceptanceStandardsTable8-2Class2AcceptanceStandardsTable8-3Class3AcceptanceStandardsTable8-4Class1,2,3ComponentSupportAcceptanceStandards.Table8-5ClassMCAcceptanceStandards....8-118-118-128-128-12File:NMP1PPB.WPD

ElYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999RECORDOFREVISIONREVISIONNo.DATESeptember27,1999AFFECTEDPAGESEntireDocumentREASONFORREVISIONUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PPB.WPD 0

NYNIAGARAVMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19998.0ACCEPTANCECRITERIAIndicationsdetectedbyinserviceexaminationsshallbecomparedagainsttheacceptancecriteriaofSectionXIasdefinedinTables8-1through8-4.8.1AcceptancebyExaminationComponentswhoseexaminationeitherconfirmstheabsenceofflaws/conditionsorrevealsindicationsthatdonotexceedtheacceptancecriteriaidentifiedinTables8-1through8-5,shallbeacceptableforcontinuedservice.Verifiedchangesofflaws/conditionsfrompriorexaminationsshallberecordedinaccordancewithSection10ofthisprogram.Acceptanceofcomponentsforcontinuedservicewithindications/conditionsexceedingtheacceptancecriteriaaboveshallbeinaccordancewiththe8.2through8.6.8.2AcceptancebyRepairComponentswhosevolumetricorsurfaceexaminationrevealsdefects/conditionsthatexceedtheacceptancecriteriaofTables8-1through8-5shallbeunacceptableforcontinuedserviceuntilremovedbymechanicalmethodsoruntilthecomponentisrepairedtothe.extentnecessarytomeettheacceptancecriteriain8.1.RepairsarefurtheraddressedinSection10.Note:TheadditionalexaminationrequirementsofIWB-2430,IWC-2430,IWE-2430orIWF-2430,(asapplicable)shallbeperformedforserviceinduceddefects/conditions,and/orthoseconstructionormanufacturingdefectsdeterminedbyNuclearEngineeringtobedetrimentaltothequalityorsafetyofthecomponent/system.8.3AcceptancebyReplacementAsanalternativetorepairrequirementsof8.2,thecomponent,ortheportionofthecomponentcontainingthedefect/conditionshallbereplaced.ReplacementsarefurtheraddressedinSection9.8.4AcceptancebyAnalyticalEvaluationComponentswhosevolumetricorsurfaceexaminationrevealsdefectsthatexceedtheacceptancecriteriaofTables8-1through8-5areacceptableforcontinuedservicewithoutdefectremoval,repairorreplacementifananalyticalevaluationmeetstheacceptancecriteriaofIWB-3600orIWC-3600asapplicable,orforClassMCmeetstheengineeringevaluationcriteriaof8.5.WheretheacceptancecriteriaofIWB-3600orIWC-3600aresatisfied,theareacontainingthedefectshallbesubsequentlyreexaminedinaccordancewith8.4.1,8.4.2or8.4.3.Note:Reexaminationshallbeaccomplishedonlyonserviceinduceddefects/conditions.Fife:NMP1PPS.WPD

LIVNIAGARA1%UMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19998.4.1Class1ComponentsPursuanttotheSectionXICode,sub-articleIWB-2420(b),inthecase,whereexaminationsrevealthepresenceofservice-induceddefectsthatexceedtheacceptancestandardsandthecomponentisanalyzedasacceptableforcontinuedservice,theareascontainingsuchdefectsshallbereexaminedduringthenextthree(3)inspectionperiodsofInspectionProgramB(IWB-2412-1).Providedthedefectsremainessentiallyunchangedforthreesuccessiveinspectionperiods,thecomponentexaminationschedulewillreverttotheoriginalscheduleofsuccessiveinspections.8.4.2Class2ComponentsPursuanttotheSectionXICode,sub-articleIWC-2420(b),inthecase,whereexaminationsrevealthepresenceofseivice-Induceddefectsthatexceedtheacceptancestandardsandthecomponentisanalyzedasacceptableforcontinuedservice,theareascontainingsuchdefectsshallbereexaminedduringthenextinspectionperiodofInspectionPlanB(IWB-2412-1).Providedthedefectsremainessentiallyunchangedforthenextinspectionperiod,thecomponentexaminationschedulewillreverttotheoriginalscheduleofsuccessiveinspections.8.4.3ClassMCComponentsWhencomponentexaminationresultsrequireevaluationofflaws,areasofdegradation,orrepairinaccordancewithIWE-3000,andthecomponentisfoundtobeacceptableforcontinuedservice,theareascontainingsuchflaws,degradation,orrepairsshallbereexaminedduringthenextinspectionperiodlistedinthescheduleofInspectionProgramB(IWE-2412-1).WhenthereexaminationrequiredbyIWE-2412(b)revealsthattheflaws,areasofdegradation,orrepairsremainessentiallyunchangedforthreeconsecutiveinspectionperiods,theareascontainingsuchflaws,degradation,orrepairsnolongerrequireaugmentedexaminationinaccordancewithTableIWE-2500-1,ExaminationCategoryE-C.8.5AcceptancebyEngineeringEvaluationExaminationsthatrevealindicationsexceedingtheacceptancecriteriaidentifiedinTables8-1through8-5willbesubmittedtoNuclearEngineeringforevaluationanddisposition:A.IndicationsfoundtobeacceptablebythematerialsandweldingcriteriaspecifiedintheConstructionCodeand/orSectionIIIEditionapplicabletotheconstructionofthecomponentshallbeacceptableforcontinuedservice.B.IndicationsdeterminedtobeacceptablebytheNMPCDesignand/orManufacturer'sSpecificationsshallbeacceptableforcontinuedservice.C.Indicationsbelievedtobesurfaceanomalies(e.g.,fabricationmarks,scratches,surfaceabrasion,materialroughnessorotherconditionsareacceptableforFile:NMP1PPB.WPD

hlVNIAGARAaUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999continuedserviceprovidedtheindicationisremovedbylightflappingand/orgrinding(surfacepreparation),andthematerialremoveddoesnotviolatethedesignminimumwallthickness.D.Iftheevaluationsconductedonacomponentsupportdemonstratesthatthesupportwasfunctionalforitsintendedsafetyfunction,additionalexamsarenotrequired.ComponentswhoseexaminationresultsrevealflawsorareasofdegradationthatexceedtheacceptancecriteriaofTable8-5areacceptableforcontinuedservicewithoutdefectremoval,repairorreplacementifanengineeringevaluationindicatesthattheflaworareaofdegradationisnonstructuralinnatureorhasnoeffectonthestructuralintegrityofthecontainment.Whensupplementalexaminationsof8.7arerequired,ifeitherthethicknessofthebasemetalisreducedbynomorethan10%ofthenominalplatethicknessorthereducedthicknesscanbeshownbyanalysistosatisfytherequirementsoftheDesignSpecifications,thecomponentshallbeacceptablebyevaluation.G.Wheretheflaworareaofdegradationareacceptedbyengineeringevaluation,the.areacontainingtheflawordegradationshallbereexaminedinaccordancewith8.4.NuclearEngineeringevaluationand/ordispositionmayincludetheneedforcorrectivemeasures,repairs,analyticalevaluation,orreplacement,asappropriate.8.6AcceptancebyCorrectionComponentsupportswhoseexaminationsrevealconditionsdescribedinIWF-3410(a)shallbeunacceptableforcontinuedserviceuntilsuchconditionsarecorrectedbyoneormoreofthefollowing:Adjustmentandreexaminationforconditionssuchas:1.Detachedorloosenedmechanicaiconnections;2.Improperhotorcoldpositionsofspringsupportsandconstantloadsupports;3.Misalignmentofsupports;or4.Improperdisplacementsettingsofguidesandstops.AcomponentsupportorportionofacomponentsupportwhichisunacceptableperTable8-4,forcontinuedservicemaybeanalyzedand/ortestedtotheextentnecessarytosubstantiateitsintegrityforitsintendedservice.File:NMP1PPB.WPD

YNlAGARA4MOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19998.7AcceptancebySupplementalExaminationVolumetric,visual,orsurfaceexaminationsthatdetectindicationsrequiringevaluationmaybesupplementedbyotherexaminationmethodsandtechniquestodeterminethecharacteroftheindication/condition.Componentscontainingindicationsand/orrelevantconditionsshallbeacceptableforcontinuedserviceiftheresultsofsupplementalexaminationsmeettheacceptancerequirementsof8.1.Examinationsthatdetectflawsorevidenceofdegradationthatrequiresevaluationinaccordancewiththerequirementsof8.5maybesupplementedbyotherexaminationmethodsandtechniques(IWA-2240)todeterminethecharacteroftheflaw(i.e.,size,shape,andorientation)ordegradation.Visualexaminationsthatdetectsurfaceflawsorareasthataresuspectshallbesupplementedbyeithersurfaceorvolumetricexamination.8.8AcceptanceCriteriainCourseofPreparationIfacceptancecriteriaforaparticularcomponent,examinationcategory,orexaminationmethodarenotspecified,defectsthatexceedtheacceptancecriteriaformaterialsandweldsspecifiedintheConstructionCodeand/orSectionIIIEditionapplicabletotheconstructionofthecomponentshallbeevaluatedtodeterminedisposition.8.9AdditionalExaminations8.9.1Class1TheadditionalexaminationrequirementsidentifiedinIWB-2430shallbeperformedforserviceinduceddefects/condition,and/orthoseconstructionormanufacturingdefectsdeterminedbyNuclearEngineeringtobedetrimentaltothequalityorsafetyofthecomponent/systemonly.Whenthissituationexists,additionalexaminationsshallincludethefollowing:Theremainingwelds,areas,orpartswithinthesameCodeItemNumberfor:1.Theexistingperiod2.Thenextsubsequentinspectionperiod,eveniftheperiodfallswithinthenextinterval.Iftheexaminationsforthatinspectionitemarenotscheduledinthesubsequentperiod,themostimmediateperiodcontainingscheduledexaminationsshallbetakenasthesubsequentperiod.C.Iftheadditionalexaminationsrevealserviceinduceddefects/conditions,theexaminationsshallbefurtherextendedtoincludeallwelds,areas,orpartsofsimilardesign,size,andfunction.File:NMP1PPB.WPD

ElYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP't-ISI-003Rev.0Date:September27,1999Additionalexaminationsofwelds,areas,orpartsmaybelimitedtowelds,areas,orpartsofsimilardesign,size,andfunction.Additionalexaminationswillbeperformedbeforetheendoftheoutage.8.9.2Class2TheadditionalexaminationrequirementsidentifiedinIWC-2430shallbeperformedforserviceinduceddetects/condition,and/orthoseconstructionormanufacturingdefectsdeterminedbyNuclearEngineeringtobedetrimentaltothequalityorsafetyofthecomponent/systemonly.Whenthissituationexists,additionalexaminationsshallincludethefollowing:a.Anadditionalnumberofcomponentsorareas,withinthesameexaminationcategory,approximatelyequaltothenumberofcomponentsorareasexaminedinitially'.b.Iftheadditionalexaminationsrevealserviceinduceddetects/conditions,theexaminationsshallbefurtherextendedtoincluderemainingnumberofsimilarcomponentsorareaswithinthesameexaminationcategory.c.Additionalexaminationsofwelds,areas,orpartsmaybelimitedtowelds,areas,orpartsofsimilardesign,size,andfunction.Additionalexaminationswillbeperformedbeforetheendoftheoutage.8.9.3Class3TherearenoadditionalexaminationrequirementsidentifiedinIWD-2000,thereforeadditionalexaminationsshallbeperformedforserviceinduceddefects/condition,and/orthoseconstructionormanufacturingdefectsdeterminedbyNuclearEngineeringtobedetrimentaltothequalityorsafetyofthecomponent/systemonly.Whenthissituationexists,additionalexaminationsshallincludethefollowing:Anadditionalnumberofcomponents'orareas,withinthesameexaminationitemnumber,system,andline,andwillincludethefollowing:2.Thenextcomponentorarea,upstreamanddownstreamoftheinitialdefectorcondition.Iftheadditionalexaminationsrevealserviceinduceddefects/conditions,theexaminationsshallbefurtherextendedtoincluderemainingnumberofsimilarcomponentsorareaswithinthesameitemnumber,systemorline.b.Additionalexaminationsofwelds,areas,orpartsmaybelimitedtowelds,areas,orpartsofsimilardesign,size,andfunction.File:NMP1PPB.WPD

hlVNIAGARAA@MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECT(ONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999Additionalexaminationswillbeperformedbeforetheendoftheoutage.8.9.4ComponentSupportsTheadditionalexaminationrequirementsidentifiedinIWF-2430shallbeperformedforserviceinduceddefects/condition,and/orthoseconstructionormanufacturingdefectsdeterminedbyNuclearEngineeringtobedetrimentaltothequalityorsafetyofthecomponent/systemonly.Whenthissituationexists,additionalexaminationsshallincludethefollowing:a.Thecomponentsupportsimmediatelyadjacenttotheinitiallyidentifiedsupportwiththedefect/condition.c.Additionalsupportsequalinnumberandsimilarintype,design,andfunctiontothoseinitiallyexamined.d.Whentheseadditionalexaminationsrevealdefect/conditions,theremainingsupportswithintheitemnumber,systemorlineshallbeexamined.,e.Additionalexaminationsofsupportsmaybelimitedtosupportswithinthesamesystemorlineofthesametype,design,andfunction.Additionalexaminationswillbeperformedbeforetheendoftheoutage.8.9.5ClassMCTheadditionalexaminationrequirementsidentifiedinIWE-2430shallbeperformedforanyoneinspectionthatrevealsflawsorareasofdegradationasfollows:ExaminationsperformedduringanyoneinspectionthatrevealflawsorareasofdegradationexceedingtheacceptancestandardsofTableIWE-3410-1shallbeextendedtoincludeanadditionalnumberofexaminationswithinthesamecategoryapproximatelyequaltotheinitialnumberofexaminationsduringtheinspection.b.WhenadditionalflawsorareasofdegradationthatexceedtheacceptancestandardsofTable8-5arerevealed,allremainingexaminationswithinthesamecategoryshallbeperformedtotheextentspecifiedinTableIWE-2500-1fortheinspectioninterval.Note:Additionalexaminationswillbeperformedbeforetheendoftheoutage.Per10CFR50.55a(b)(x),NMPCshallevaluatetheacceptabilityofinaccessibleareaswhenconditionsexistinaccessibleareasthatcouldindicatethepresenceoforresultindegradationtosuchinaccessibleareas.TheevaluationsshallincludeFile:NMP1PPB.WPD

NineMilePointNuclearPowerStationUnit1NMP1-Isl-003VNIAGARAUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999areaswhenconditions,existinaccessibleareasthatcouldindicatethepresenceoforresultindegradationtosuchinaccessibleareas.Theevaluationsshallincludethefollowinginformation:A.Adescriptionofthetypeandestimatedextentofdegradation,andtheconditionsthatledtothedegradation;B.Anevaluationofeacharea,andtheresultsoftheevaluation,and;C.Adescriptionofnecessarycorrectiveactions.8.9.6IGSCCSampleExpansionIfoneormorecrackedweldsinIGSCCCategoriesA,B.orC,arefoundbyasampleinspectionduringthe10yearinterval,anadditionalsampleoftheweldsinthatcategoryshouldbeinspected,approximatelyequalinnumbertotheoriginalsample.Thisadditionalsampleshouldbesimilarindistribution(accordingtopipesize,system,andlocation)totheoriginalsample,unlessitisdeterminedthatthereisatechnicalreasontoselectadifferentdistribution.Ifanycrackedweldsarefoundinthissecondsample,alloftheweldsinthatIGSCCCategoryshouldbeinspected.B.Ifsignificantcrackgrowth,oradditionalcracksarefoundduringtheinspectionofoneormoreIGSCCCategoryEwelds,allotherCategoryEweldsshouldbeexamined.Significantcrackgrowthforoverlayedweldsisdefinedascrackextensiontodeeperthan75%oftheoriginalwallthickness,orforcracksoriginallydeeperthan75%ofthepipewall,evidenceofcrackgrowthintotheeffectiveweldoverlay.b.SignificantcrackgrowthforSlmitigatedCategoryEweldsisdefinedasgrowthtoalengthordepthexceedingthecriteriaforSlmitigation.(10%ofcircumferenceor30%indepth).C.CategoryDweldexpansionsarelimitedtopipingsystemswherecrackingwasidentified.8.10DefectsFoundOutsideSectionXIExaminationDefects/conditionsthatarefoundoutsidethecourseofaSectionXIexamination,shallbecomparedagainsttheacceptancestandardsofTables8-1through8-4,asapplicable.File:NMP1PPB.WPD

YNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999"'-'::."';"'>A':""'-;"-"'TABLES-1'-'L'ASS1'ACCEPTANCE'STANDARDS-'.."-"""EXAMINATION;j;:~r~";;;,>'-':--CQMPONENTORPART;:,EXAMINED.:,-=-'--;=-':-;""';:",:;-..ACCEPTANCE,";;;;;;"","'CATEGORY,'-.":".::.-.:~"~."-""'-':,"'.'"i'8"".'.'"--"",""'l".;"'i.--:S1ANDARD'k'-AB-BB-DB.EB-F,B-JB-G-1B-G-2B-H.B-K-1B-L-1.B-M-1B-L-2.B-M-2B-N-1B-N-2B-N-3B-0B-PB-QWeldsinReactorVesselsWeldsinOtherVesselsVesselNozzleWeldsPartialPenetrationweldsinVesselsDissimilarandSimilarMetalWeldsinPiinBoltin>2'dia.Boltin<2'dia.InteralAttachmentsforPiin,Valves,Pums8VesselsWeldsinPums8ValvesPumCasins&ValveBodiesInteriorSurfaces8InternalComponentsofReactorVesselsControlRodDriveHousinWeldsPressureRetaininBoundaSteamGeneratorTubinIWB-3510IWB-3510IWB-3512IWB-3522IW8-3514IWB-3515/3517IW8-3517IW8-3516IWB-3518IWB-3519IW8-3520.1IW8-3520.2IW84523IWB-3522IWB.3521TABLE8 CLASS2ACCEPTANCESTANDARDSEXAMINATIONCATEGORYC-AC-BC-CC-DC-F-1,C.F-2C-GC-HCOMPONENTORPARTEXAMINEDWeldsinPressureVesselsNozzleWeldsinVesselsInteralAttachmentsforVessels.Piin,PumsandValvesBoltinWeldsinPiinWeldsinPumsandValvesPressureRetaininComonentsACCEPTANCESTANDARDIWC-3510IWC-3511IWC-3512IWC-3513IWC-3514IWC-3515IWC-3516Fife:NMP1PPB.WPD

NineMilePointNuclearPowerStationUnlt1NMP1-ISI-003HYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999EXAMINATIONCATEGORYD-AVAEILEse-CLASS3ACCETANCESTANDARDSCOMPONENTORPARTEXAMINEDIntegralAttachments(VT-1)ACCEPTANCESTANDARDMlg.Code8ApplicablendfdASMESectionXIAcceptanceStandardincourseofpreparation.TABLE8<-COMPONENTSUPPORTACCEPTANCESTANDARDSEXAMINATION"'ATEGORY'-ACOMPONENTORPARTEXAMINEDSupportsACCEPTANCESTANDARDIWF-3410EXAMINATIONCATEGORYE-AE-BE-CTABLE'SW"-".CL'ASS'CACCEPTANCESTANDARDSCOMPQNENTORPARTEXAMINEDContainmentSurfacePressureRetaininWeldsContainmentSurfacesrequiringAugmentedExaminationsACCFPTANCESTANDARDIWE-3510IWE-3511IWE-3512E-DE-FE-GE-PSeals,gaskets,andmoisturebarriersPressureretainingdissimilarmetalwefdsPressureretainingboltingAllressureretafnincornnentsIWE-3513IWE-3514IWE-3515AendixJFife:NMP1PPS.WPD

EIYNIAGARAHI!MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTSSECTION9-REPAIRS,REPLACEMENTS,MODIFICATIONSTableofContents9-1RecordofRevision9-39.0REPAIRS,REPLACEMENTSANDMODIFICATIONS9.1Repairs9.1.1Exemptions9.1.2RepairOperations9.1.3PressureTesting9.1.4,BaselineExaminations9.2Replacements9.2.1ReplacementOperations..9.2.2EngineeringApproval..9.2.3PressureTesting9.2.4PreserviceExaminations9.3Repair/ReplacementActivitiesforIWEClassMCComponents9.3.1IWEExemptComponents9.3.2IWEClassMCComponentsOperations9.3.3IWEClassMCComponentsExaminationRequirements..9.3.4IWEClassMCComponentsExaminationandPressureTestRequirements.9.3.5IWEClassMCComponentsExaminationQualifications9-49-49-49-59-59-59-59-59-69-69-79-79-79-79-89-89-8File:NMP1PP9.WPD

HYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.4Modifications9.5Evaluation9.6AccessTABLEOFCONTENTS(Continued)9-89-89-99.7ConstructionCodes9.8AuthorizedNuclearInserviceInspector9.9Implementations9-99-99-9File:NMP1PP9.WPD

HYNlAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REVISIONNo.RECORDOFREVISIONAFFECTEDPAGESREASONFORREVISIONSeptember23,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:NMP1PP9.WPD

VNIAGARA&MOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.0REPAIRS,REPLACEMENTSANDMODIFICATIONSScopeThissectionestablishestheprogrambywhichtheNineMilePointNuclearPowerStationwilldefinethemanagerialandadministrativecontrolsovertheimplementationandcompletionofrepairs,replacement(modifications)andmaintenanceofitemsthatrequiresubsequentinserviceexaminationsortests.ThissectionimplementstherequirementsoftheASMEBoilerandPressureVesselCode,SectionXI,"RulesforInserviceInspectionofNuclearPowerPlantComponents,"hereafterreferredtoastheCode,1989Edition,noAddenda,fortheRepair,Replacement(modification),andInstallationofReplacementActivitiesattheNineMilePointNuclearPowerStation.TherepairsandreplacementsforcomponentswhicharewithintheprovisionsofASMEBoilerandPressureVesselCode,SectionXI,1992Editionwiththe1992AddendaofSubsectionIWE,"RequirementsforClassMCMetallicLinersofClassCCComponentsofLight-WaterCooledPowerPlants,"incorporatedbyreferencein10CFR50.55a,willbecontrolledinaccordancewiththisprogram.TherepairsandreplacementsforwhichtheseprovisionsapplyarerestrictedtothoseperformedonsystemsandcomponentsclassifiedClass1,2,3,andClassMCpressureretainingcomponentsandtheirintegralattachments.ASMESectionXIRepairsandReplacementsshallbeconductedinaccordancewiththeNiagaraMohawkPowerCorporationimplementingRepair/Replacementprocedures.9.1RepairsRepairsforwhichtheseprovisionsapplyarerestrictedtothoseperformedonsystemsandcomponentsclassifiedQualityGroupA,BorC,(Class1,2,3)andClassMCpressureretainingcomponentsandtheirintegralattachments.RepairsshallbeperformedinaccordancewithNMPC'sNMP1DesignSpecificationandtheoriginalConstructionCodeofthecomponentorsystem.However,asallowedbyparagraphIWA-4120,laterEditionsandAddendaoftheConstructionCodeorofSectionIII,eitherintheirentiretyorportionsthereof,andCodeCasesmaybeused.ThelatereditionsandAddendaofSectionXI,eitherintheirentiretyorportionsthereof,maybeusedfortherepairprogram,providedtheseEditionsandAddendaofSectionXIatthetimeoftheplannedrepairhavebeenincorporatedbyreferenceinamendedregulationsoftheregulatoryauthorityhavingjurisdictionattheplantsite.9.1.1ExemptionsTherepairofpiping,valvesandfittings,nominalpipesize(1)oneinchandlessareexemptfromNDEandpressuretesting,butshallcomplywithallotherrulesofthissection.Theserepairsshallbemadeinaccordancewiththeapplicableplantprocedureforrepair/replacementandmeettherequirementsoftheNMPCQualityAssuranceProgram.File:NMP1PP9.WPD

HTNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.1.2RepairOperationsCoderepairsareperformedinaccordancewithapprovedproceduresorinstructionsthatmeettherequirementsofIWA-4000.Repairoperationsshallbeperformedinaccordancewithaprogramdelineatingrequirementsofthecompleterepaircycleandshallincludethefollowing:(a)TheNDEmethodthatrevealedtheflawandthedescriptionoftheflaw.(b)Theflawremovalmethod,methodofmeasurementofthecavitycreatedbyremovingtheflawanddimensionalrequirementsforreferencepointsduringandaftertherepair.(c)Weldproceduresandpostweldheattreatment,andthenon-destructiveexaminationprogramtobeusedaftertherepair.(d)Evaluationasdescribedin9.5.(e)Therepairprogramsshallbesubjecttoreviewbytheenforcementandregulatoryauthoritieshavingjurisdictionattheplantsite.9.1.3PressureTestingAfterrepairsbyweldingonthepressureretainingboundary,apressuretestshallbeperformedinaccordancewiththerequirementsoftheInservicePressureTestingProgram,DocumentNMP1-PT-003.9.1.4BaselineExaminationsWhenrequiredbySectionXl,therepairedareashallbereexaminedtoestablishanewpreservicerecord.Theexaminationshallincludethemethodthatdetectedtheflaw.9.2ReplacementsReplacementsareperformedusingapprovedproceduresorinstructionsinaccordancewithIWA-7000.Allproceduresfortheinstallationofrenewal,spare,andreplacementpartsshallbeinaccordancewithIWA-4100.Alternatively,subsequentEditionsandAddendaofSectionXImaybeusedforreplacementprovidedtheseEditionsandAddendaareacceptabletotheenforcementandregulatoryauthoritieshavingjurisdictionatthesite.9.2.1ReplacementOperationsTheprogramforreplacementsshallincludethefollowing:(a)TheapplicableConstructionCodetowhichtheoriginalitemwasconstructedFile:NMP1PP9.WPD

VNIAGARAMOHAWKNirieMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999(b)Theexistingdesignrequirements(iftheoriginalitemwasconstructedwithoutCoderequirements,theitemtobeusedforreplacementshallbeinaccordancewiththedesign,fabrication,andexaminationrequirementsfortheoriginalitemunlessthealternativeof(c)belowisadopted).(c)Alternatively,anitemtobeusedforreplacementmaymeetallorportionsoftherequirementsoflatereditionsoftheConstructionCodeorSectionIII,whentheConstructionCodewasnotSectionIII,providedthatthefollowingrequirementsaremet.(1)Therequirementsaffectingthedesign,fabrication,andexaminationoftheitemtobeusedforreplacementarereconciledwiththeOwner'sthroughtheStressAnalysisReport,DesignReport,orothersuitablemethodthatdemonstratestheitemissatisfactoryforthespecifieddesignandoperatingconditions.(d)Adescriptionoftheworktobeperformed.(e)TheCodeEdition,AddendaandCodeCasesapplicabletomaterials,designmanufacture,andinstallation.,(f)Anyspecialrequirementspertainingtomaterials,welding,heattreatment,andnondestructiveexaminationrequirements.(g)Mechanicalinterfaces,fits,andtolerancesthatprovidesatisfactoryperformancearecompatiblewithsystemandcomponentrequirements.(h)Materialsarecompatiblewithinstallationandsystemrequirements.(I)Thetestandacceptancecriteriatobeusedtoverifytheacceptabilityofthereplacement.(j)ThedocumentationrequiredbyIWA-7500.(k)TheapplicationoftheASMENACodeSymbolStampisneitherrequirednorprohibitedfortheinstallationofaitemtobeusedforreplacement.9.2.2EngineeringApprovalReplacementsthatinvolvesubstitutionofmaterials,dimensionalchanges,processchanges,deviationstospecificationsorchangestodesigncodesrequireengineeringapproval.9.2.3PressureTestingPressuretestingshallbeperformedonreplacementsinaccordancewiththeInservicePressureTestingProgram,DocumentNMP1-PT-003.File:NMP1PP9.WPD

hlYNIAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.2.4PreserviceExaminationsPriortothesystem'sreturntoservice,apreseiviceinspectionshallbemadeinaccordancewithIWB-2200,IWC-2200,IWD-2200,IWF-2200,IWE-2200.Post-WorktestingandpressuretestingwillbeperformedasdelineatedinapplicablePlantProcedure(s).9.3Repair/ReplacementActivitiesforIWEClassMCComponentsTheUSNRCamended10CFR50.55a,byreferencethe1992Editionwiththe1992AddendaofSectionXI,toincorporatesubsectionIWE-"RequirementsforClassMCandMetallicLinersofClassCCComponentsofLight-WaterCooledPowerPlants",andSubsectionIWL-RequirementsforClassCCConcreteComponentsofLight-WaterCooledPowerPlants".Note:SubjectIWLisnotapplicabletoNineMilePoint¹clearPowerStation,astheNMP1Plantusesasteelprimarycontainment.9.3.1IWEExemptComponentsThefollowingcomponents(orpartsofcomponents)areexemptedfromtheexaminationrequirementsofIWE-2000:(a)Vessels,parts,andappurtenancesthatareoutsidetheboundariesofthecontainmentasdefinedintheDesignSpecifications;(b)Embeddedorinaccessibleportionsofcontainmentvessels,parts,andappurtenancesthatmettherequirementsoftheoriginalConstructionCode;(c)Portionsofcontainmentvessels,parts,andappurtenancesthatbecomeembeddedorinaccessibleasaresultofvesselrepairorreplacementiftheconditionsofIWE-1232andIWE-5220aremet;(d)Piping,pumps,andvalvesthatarepartofthecontainmentsystem,orwhichpenetrateorareattachedtothecontainmentvessel.ThesecomponentsshallbeexaminedinaccordancewiththerulesofIWBorIWC,asappropriatetotheclassificationdefinedbytheDesignSpecifications.9:3.2IWEClassMCComponents-OperationsTheprogramforClassMCcomponentsandtheirintegralattachmentsforRepair/Replacementsshallincludethefollowing:(a)ThePrimalyContainmentSystematNMP1,whichisdefinedasaGeneralElectricMark1PressureSuppressionContainment.File:NMP1PP9.WPD

hlVNlAGARAIiUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.3.3IWEClassMCComponentsExaminationRequirements(a)ExaminationrequirementsshallapplytoClassMCpressureretainingcomponentsandtheirintegralattachments.Theseexaminationsshallapplytosurfaceareas,includingweldsandbasemetal.Note:Pursuantto10CFR50.55a(b)(2)(x)(C)examinationofpressureretainingweldsandpressureretainingdissimilarmetalweldsareoptional.(b)PreserviceExaminationsshallbeperformedinaccordancewiththerequirementsdefinedinIWE-2200,PreserviceExamination.(c)VisualexaminationsperformedduringtheconductofasystempressuretestshallbeinaccordancewithInservicePressuretestingProgram,DocumentNMP1-PT-003.9.3.4IWEClassMCExaminationandPressureTestRequirementsExaminationandPressureTestrequirementsshallbeperformedinaccordancewiththerequirementsdefinedinIWE-2500,ExaminationandPressureTestRequirements,IWE-5200,SystemTestRequirements,applicableCodeCasesthatareapprovedforuseandacceptedforimplementationwithintheISIRepair/ReplacementProgram,orapprovedUSNRCReliefRequestsforthecomponentand/orpart.9.3.5IWEClassMCComponentsExaminationQualificationsExaminationqualificationsshallmeetthoserequirementsofIWA-2300,applicableCodeCasesthatareapprovedforuseandacceptedforimplementationwithintheISIRepair/ReplacementProgram,orUSNRCapprovedReliefRequestsasapplicable.9.4ModificationsTheperformanceofmodificationsiscontrolledinaccordancewithapplicableplantprocedures.9.5EvaluationWhentherepair,replacementormodificationisrequiredbecauseoffailureofapartorcomponentpressureboundary,anevaluationshallbedonetoensurethatthereplacementissuitableandtherepairprocedureselectedissuitable.ThecauseoffailureshallbeevaluatedinaccordancewiththeCode.Engineeringevaluationsshallbeusedtodocumentconditionaluseofequipment("useasis")orequipmentsubstitutionswhenitisimpracticaltorestoretheequipmenttotheoriginaldesignconfigurationbymodification,repair,ordirectreplacement.Note:RefertoSection8ofthisprogramforspecificcriteriafortheacceptanceandevaluationofIWB,IWC,IWD,IWF,andIWEcomponents/systems.File:NMP1PP9.WPD

ElYNIAGARAa@MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,19999.6AccessAccessibilityforinserviceinspectionwasconsideredduringthedesignofthereactorvesselandinsulationtoensureadequateworkingspaceandaccessforinspection.TheselectionofthecomponentsandlocationstobeinspectedmeettheintentoftheASMEBoilerandPressureVesselCode,SectionXI,"InserviceInspectionofNuclearReactorCoolantSystems",datedJanuary1,1970.AdequateaccessandclearancesforexaminationandtestsshallbeconsideredbyNuclearEngineeringaspartoftheprocessingofdesignorarrangementchangesofsystemcomponentsinaccordancewithapplicableNuclearEngineeringProcedures/Instructions.9.7ConstructionCodesTheprocurement,design,fabricationandinstallationComponents,parts,andpipingshallbeinaccordancewiththerequirementsoftheFSARanddesignspecifications.LaterEditionsandAddendaoftheConstructionCodeorofSectionill,eitherintheirentiretyorportionsthereof,andCodeCasesmaybeused.WeldingactivitiesshallbeperformedinaccordancewithNMPCWeldControlManual.9.8AuthorizedNuclearInserviceInspectorTheservicesofanAuthorizedNuclearInserviceInspector(ANII)shallbeusedwhenmakingallrepairs/replacements.TherepairplannershallbemadeavailableforreviewbytheANIIforallweldedrepairs/replacements.TheANIIshalldeterminewhatholdpoints,ifany,arerequiredtomonitortherepair/replacementactivity.NMPCshallnotifytheANIIpriortostartingtherepair,replacementormodificationandkeeptheinspectorinformedoftheprogressoftheworksothatnecessaryinspectionsmaybeperformed.9.9ImplementationAllASMESectionXIClass1,2and3RepairsandReplacementsarecontrolledbysiteprocedures.File:NMP1PP9.WPD

NineMilePointNuclearPowerStationUnit1NMP1-ISI-003YNIAGARA4MOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999TABLEOFCONTENTSSECTION10-RECORDSTableofContentsRecordofRevision10.0RECORDS10.1General10.2InserviceInspectionSummaryReport10.3CoverSheet10.4SummaryReportSubmittal10.5ReportingRequirementsforIGSCC10.6ReportingRequirementsforClassMC10.7ReportingRequirementsforNUREG061910-110-210-310-310-310-310-410-410-410-4LISTOFFIGURES10-1NIS-1Owners'ataReportforInserviceInspections10-2NIS-2Owners'eportforRepairsandReplacements.10-3OAR-1Owner'sActivityReport.Table1-AbstractofExaminationandTests..Table2-ItemswithFlawsorRelevantConditionsthatRequireEvaluationforContinuedService10-610-810-1010-1110-12Table3-AbstractofRepairs,ReplacementsorCorrectiveMeasuresRequiredforContinuedService10-4NIS-2ARepair/ReplacementPlanCertificationRecord10-1310-14File:NMP1PP10.WPD

VNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REVISIONNo.-.RECORDQF,REVISION'AFFECTED"<<",PAGESREASONFOR'RFVISION0September27,1999EntireDocumentUpdatedInserviceInspectionprogramPlanforthe3"0TenYearInserviceInspectionIntervalFile:NMP1PP10.WPD

hlV'lAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,199910.0RECORDSThissectionprovidestherequirementsforthepreparationandsubmittalofInserviceInspectionrecordsandreportsasrequiredbyIWA-6000.10.1GeneralExaminations,tests,replacements,andrepairrecordsarepreparedinaccordancewiththerequirementsoftheASMEBoilerandPressureVesselCode,SectionXI.10.2InserviceInspectionSummaryReportAnInserviceInspectionSummalyReportwillbepreparedatthecompletionofeachinspectionconductedduringarefuelingoutage.Examinations,tests,replacements,andrepairsconductedsincetheprecedingsummaryreportshallbeincluded.Note:AsaalternatetotherequirementsofIWA-6000,NMPChassubmittedaRequestforRelieftoimplementCodeCaseN-532,"AlternativeRequirementstoRepairandReplacementDocumentationRequirementsandInserviceSummaryReportPreparationandSubmissionasRequiredbyIWA-4000andIWA-6000,SectionXI,Division1".\EachSummaryReportwillcontainthefollowing:a.Refuelingoutagenumber(whenapplicable).b.Owner'sDataReportforInserviceInspections,FormNIS-1,Figure11-1orFormOAR-1,Figure10-3.c.Owner'sDataReportforRepairsorReplacementsFormNIS-2orFormNIS-2A,Figure11-2andFigure11-3.SubjecttoRequestforRelief:ISI-S10.3CoverSheetEachSummaryReportwillhaveacoversheetprovidingthefollowinginformation:a.Dateofdocumentcompletionb.NameandaddressofOwnerNameandaddressofgeneratingplantNameandnumberdesignationoftheplantCommercialservicedatefortheunitFile:NMP1PP10.WPD

YNlAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,199910.4SummaryReportSubmittalNinety(90)daysfollowingtheunitsreturntoservice,NMPCshallforwardaSummaryReportoftheInserviceInspectionactivitytotheUnitedStatesNuclearRegulatoryCommissioninaccordancewithIWA-6220,ortherequirementsspecifiedinCodeCaseN-532,uponUSNRCapproval.10.5ReportingRequirementsforIGSCCIfanycracksareidentifiedthatdonotmeetthecriteriaforcontinuedoperationwithoutevaluationgiveninSectionXloftheCode,USNRCapprovalofflawevaluationand/orrepairsinaccordancewithIWB-3000andIWA-4000isrequiredbeforeresumptionofoperation.10.6ReportingRequirementsforClassMCPer10CFR50.55a(b)(x),NMP1shallprovidethefollowingintheInserviceInspectionSummaryReportrequiredbyIWA-6000:(1)Adescriptionofthetypeandestimatedextentofdegradation,andtheconditionthatledtothedegradation;(2)Anevaluationofeacharea,andtheresultsoftheevaluation,and;(3)Adescriptionofnecessalycorrectiveaction.10.7ReportingRequirementsforNUREG0619Within6monthsofcompletinganoutageatwhichtheseexaminationswereperformed,NMP1mustsubmitadetailedreporttotheNRCRegionalDirector,IE,withcopiestotheDirector,IE,andDirector,NRR;discussingtheinspectionsperformed,including:Thenumberofstartup/shutdowncyclessincethepreviousinspection,andthetotalnumberofcycles.Thisincludescyclesaccumulatedduringtheinitialstartupandtestingoftheplant.2.ASummaryofmethodsusedandresultsofpreviousinspections,includingmaximumcrackdepth,numberofcracksfound,andnumberofstartup/shutdowncyclesbetweensuchinspections.AdescriptionofanyadditionalsystemchangesorchangesinoperatingproceduresthatwillaffectFeedwaterflowortemperatureandthatshouldbeconsideredinpredictingfuturecrackingtendenciesbasedonpasthistory.Adetaileddiscussionoftheinspectionresults,includingacompletedescriptionofcrackinglocations,dimensions,andacrackprofile.TheUSNRC,ifavailable,requestsdrawingsandphotographs.Informationregardingtheresultsofleakagemonitoring.However,theUSNRCstaffmustbeFile:NMP1PP10.WPD

ElYN(AGARAaUwoHAwKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999informedimmediatelyifon-lineleakagemonitoring,duringoperations,disclosesanyleakagefromweldedspargers,orleakageontheorderof0.3gpmthroughsingle-sleeve/single-piston-ringspargersortriplesleevespargers.InformationregardingallUTcrack-likeindicationsandanysubsequentPTindications.InformationregardingUTtechniquesshouldbeaspreciseandasextensiveaspossibleinorderthatitmaybeofbenefitinfutureinspections.File:NMP1PP10.WPD

EIYNIAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999FIGURE10-1FORMNIS-1OWNERS'ATAREPORTFORINSERVICEINSPECTIONSAsreuiredbtheProvisionsoftheASMECodeRules1.Owner:(NameandAddressofOwner)W2.Plant:NinirinPYr1(NameandAddressofPlant)3.PinotUnit:~4.OwnerOertlficeteofAuthorlzetlon(tfrequired)5.CommercialServiceDate:~~QQQQ6.NationalBoardNumberforUnit:~~7.ComponentsInspected:rompnonnent',or,'rtentuan'n'Ced'-.'-;.'"'anufactui'er'or'.'nstaller..Manufactu'rer'o'r',c'nstallerSerialNo.Stateor'Pro'vfn'c'eNo.NartionalBoar'dNo.'Note:Supplementalsheetsinformoflists,sketches,ordraviingsmaybeused,provided(1)sizeis8thx11in.(2)informationinitems1through6onthisreportisincludedoneachsheet,and(3)eachsheetisnumberedandthenumberofsheetsisrecordedatthetopofthisform.File:NMP1PP10.WPD

ElYNIAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999FIGURE10-1(Continued)NIS-1Owner'sDataReportFORMNIS-1(Back)8.ExaminationDates:to9.InspectionPeriodIdentification:10.InspectionIntervalIdentification:11.ApplicableEditionofSectionXI:12.Date/RevisionofInspectionPlan:13.AbstractofExaminationsandTests.IncludealistofexaminationsandtestsandastatementconcerningstatusofworkrequiredforinspectionPlan.14.AbstractofResultsofExaminationsandTests.15.AbstractofCorrectiveMeasures.Wecertifythata)thestatementsmadeinthisreportarecorrectb)theexaminationsandtestsmeettheInspectionPlanasrequiredbytheASMECode,SectionXI,andc)correctivemeasurestakenconformtotherulesoftheASMECode,SectionXI.CertificateofAuthorizationNO.(Ifapplicable)Date19SignedOwnerbyExpirationDateCERTIFICATEOFINSERVICEINSPECTIONI,theundersigned,holdingavalidcommissionissuedbytheNationalBoardofBoilerandPressureVesselInspectorsand/ortheStateorProvinceofandemployedbyhaveinspectedthecomponentsdescribedinthisOWNERS'ataReportduringtheperiodto,andstatethattothebestofmyknowledgeandbelief,theOwnerhasperformedexaminationsandtakencorrectivemeasuresdescribedintheOwners'ataReportinaccordancewiththerequirementsoftheASMECode,SectionXI.Bysigningthiscertificate,neithertheinspectornorhisemployermakesanywarranty,expressedorimplied,concerningtheexaminations,andneithertheinspectornorhisemployershallbeliableinanymannerforanypersonalinjuryorpropertydamageorlossofanykindarisingfromorconnectedwiththisinspection.Date:Inspector'sSignature~19CommissionNumberNationalBoard,State,Province,andEndorsementsFile:NMP1PP10.WPD

NYNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1<<ISI-003Rev.0Date:September27,1999FIGURE10-2FORMNIS-2OWNERS'EPORTFORREPAIRSORREPLACEMENTSAsReuiredbtheProvisionsoftheASMECodeSectionXi1.Owner:NameinDate:BIvAddressY1Sheetof2.Plant:NameUnit:(RepairOrganizationP.O.No.,JobNo.,etc.)3.WorkPerformedBy:NameTypeCodeSymbolStamp:AuthorizationNo.:ExpirationDate:Addresse4.IdentificationofSystem:5.(a)ApplicableConstructionCode:EditionAddendaCodeCase(b)ApplicableEditionofSectionXIUtilizedforRepairorReplacement196.IdentificationofcomonentsRealrodorRelacedandReIacementComonentstramsolComponentttsmoofatsnufacturorMsnutacturerSerialkumberttatlonatBoardtto.othortdontlflcstlonYearBuiltReplacedttepalrednelscementASMBCodeStampedearNo7.DescriptionofWork:8.TestConducted:HydrostatIc[]Pneumatic[]NominalOperatingPressure[]OTHER[]Pressure:PslTestTemp:DegreeFtNOte:Supplementalsheetsinformoflists,sketches,ordrawingsmaybeused,provided(1)sizeis8trax11in.(2)informationinitems1through6onthisreportisincludedoneachsheet,and(3)eachsheetisnumberedandthenumberofsheetsisrecordedatthetopofthisform.File:NMP1PP10.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003HYNIAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999FIGURE10-2(CONTINUED)NIS-2REPORTCONTINUED9.Remarks:AppficabfeManufacturer'sDataReportstobeattachedCERTIFICATEOFCOMPLIANCEWecertifythatthestatementsmadeinthereportarecorrectandthisconformstotherulesoftheASMECodeSectionXI.TypeCodeSymbolStamp:N/A(Repair/Replacement)CertificateofAuthorizationNo.:SignedOwnerorOwners'esignee,TitleExpirationDate:Date,19CERTIFICATEOFINSERVICEINSPECTIONI,theundersigned,holdingavalidcommissionissuedbytheNationalBoardofBoilerandPressureVesselInspectorsandtheStateorProvinceofandemployedbyofhaveinspectedthecomponentsdescribedinthisOwners'eportduringperiodto,andstatethattothebestofmyknowledgeandbelief,theOwnerhasperformedexaminationsandtakencorrectivemeasuresdescribedinthisOwners'eportinaccordancewiththerequirementsoftheASMECode,SectionXI.BysigningthiscertificationneithertheInspectornorhisemployermakesanywarranty,expressedorimplied,concerningtheexaminationsandcorrectivemeasuresdescribedinthisOwners'eport.Furthermore,neithertheInspectornorhisemployershallbeliableinanymannerforanypersonalinjuryorpropertydamageorlossofanykindarisingfromorconnectedwiththisinspection.Inspector'sSignatureCommissionsNationalBoard,State,ProvinceandEndorsementsDATE:,19File:NMP1PP10.WPD

hlTNIAGARAl14MOHAWKNineMilePofntNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1<<ISI-003Rev.0Date:September27,1999ReportNumberOwnerPlantIrP(NameandAddressofOwner)(NameandAddressofPlant}FIGURE10-3FORMOAR-1OWNER'SACTIVITYREPORTAsrequiredbytheprovisionsoftheASMECodeCaseN-S32PageofPlantUnit~CommercialServiceDateCurrentInspectionIntervalCurrentInspectionPeriod(1st,2nd,3rd,4th,Other)(1st,2nd,3rd)RefuelingOutageNumberEditionandAddendaofSectionXIapplicabletotheInspectionPlanDateandRevisionofinspectionPiannandAddendaofASMESectionXIapplicabletoRepairsandReplacements,ifdifferentthanspectionPlanCERTIFICATEOFCONFORMANCEIcertifythatthestatementsmadeinthisOwner'sActivityReportarecorrect,andthattheexaminations,tests,repairs,replacements,evaluationsandcorrectivemeasuresrepresentedbythisreportconformtotherequirementsofSectionXI.CertificateofAuthorizationNo.(Ifapplicable)ExpirationDateSigned(Owner'sRepresentativeandTitle)DateCERTIFICATEOFINSERVICEINSPECTIONI,theundersigned,holdingavalidcommissionissuedbytheNationalBoardofBoilerandPressureVesselInspectorsandtheStateorPrownceofandemployedbyofhaveinspectedtheitemsdescribedinthisOwner'sActivityReport,duringtheperiodto,andstatethattothebestofmyknowledgeandbelief,theOwnerhasperformedallactivitiesrepresentedbythisreportinaccordancewiththerequirementsofSectionXI.BysigningthiscertificateneithertheInspectornorhisemployermakesanywarranty,expressedorimplied,concerningtheexaminations,tests,repairs,replacements,evaluationsandcorrectivemeasuresdescribedinthisreport.Furthermore,neithertheInspectornorhisemployershallbeliableinanymannerforanypersonalinjuryorpropertydamageoralossofanykindarisingfromorconnectedwiththisinspection.DateInspector'sSignature19CommissionsNationalBoard,State,Province,andEndorsementsFile:NMPtPP10.WP0

TNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999FIGURE10-3(Continued)TABLE1ABSTRACTOFEXAMINATIONANDTESTSAsrequiredbytheprovisionsoftheASMECodeCaseN-532PageofCODEEXAMINATIONCATEGORYTOTALEXAMINATIONSREOUIREDFORINTERVALTOTALEXAMINATIONSREQUIREDFORTHISPERIODTOTALEXAMINATIONSCREDITED(%)FORTHEPERIODTOTALEXAMINATIONSCREDITED(%)ToDATEFORTHEINTERVALREMARKSNOTAPPUCABLETONINEMILEPOINTNUCLEARPOWERSTATIONUNITI37BGINOTAPPLICABLETONINEMILEPOINTNUCLEARPOWERSTATIONUNIT1.THISCATEGORYHASBEENCOMBINE0WITHCATEGORYB.KPERCOOECASEN.509BJCODECASEN-509APPUESNOTAPPLICABLETONINEMILEPOINTNUCLEARPOWERSTATIONUNITIBMIBM.217WHENDISSEMBLEDB.N.276B.N-30NINEMILEPOINTNUCLEARPoNOTAPPUCABLETWERSTATIONUNITIC.C105CODECASEN.509APPUESCFI62C-F-2C.GDA487CODECASEN509APPUESCODECASEN491~IAPPLIESFile:NMP1PP10.WPD

VNlAGARA4MOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999FIGURE10-3(ContinLted)TABLE2ITEMSWITHFLAWSORRELEVANTCONDITIONSTHATREQUIREEVALUATIONFORCONTINUEDSERVICEAsrequiredbytheprovisionsoftheASMECodeCaseN-532PageofEXAMINATIONCATEGORYB-JB-JB-JB-JB-JB-AB-AITEMNUMBERB9.11ITEMDESCRIPTION32-WD-050ValvetoPieB9.1132-WD-126N1DNoz.SEtoElbowB9.1132-WD-168N1ENoz.SEtoElbowB9.11.32-WD-046N1BNoz.SEtoElbowB9.1132-WD-086N1CNoz.SEtoElbowB1.12RV-WD-140LowerVesselLonWeldB1.30RV-WD-099ShelltoFlaneWeldFLAWCHARACTERIZATION(IWA.3300)IWB-3600IWB-3600IWB-3600IWB-3600IWB-3600IWB-3600IWB-3600FLAWORRELEVANTCONDITIONFOUNDDURINGSCHEDULEDSECTIONXIEXAMINATIONORTESTESORNOYesYesYesYesYesYesYesFile:NMP1PP10.WPD

NineMllePointNuclearPowerStationUnit1NMP1-ISI-003hlYNlAGARAHUMOHAWKTHIRDINSERVICEINSPECTIONINTERVALRev.0INSERVICEINSPECTIONPROGRAMPLANDate:September27,1999FIGURE10-3(Continued)TABLE3ABSTRACTOFREPAIRS,REPLACEMENTS,ORCORRECTIVEMEASURESREQUIREDFORCONTINUEDSERVICEAsrequiredbytheprovisionsoftheASMECodeCaseN-532PageofCODECLASSREPAIRREPLACEMENTORCORRECTIVEMEASUREITEMDESCRIPTIONDESCRIPTIONOFWORKFLOWORRELEVANTCONDITIONFOUNDDURINGSCHEDULEDSECTIONXIEXAMINATIONORTEST(YESORNO)DATECOMPLETEREPAIRREPLACEMEI4T*PLANNUMBERFile:NMP1PP10.WPD

hlVNlAGARAaUMOHAwKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999FIGURE10-4FORMNIS-2AREPAIR/REPLACEMENTPLANCERTIFICATIONRECORDAsrequiredbythoprovisionsofthoASMSCodoCaseN-532Pagoofasaaaaaaaaasaaaaasassssssssssaaaaaassasaaassassasaaaaaaaasassasassssaaaaasaaasaasassassasaaaaasaasaaassaaasaasasaa-aaasaaaaIcertifythattheOWNER'SCERTIFICATEOFCOMPLIANCErepresentedbyRepair/ReplacementrepairorreplacementPlanNumberconformstothorequirementsofSectionXI.TypeCodeSymbolStampCertificateofAuthorizationNo.ExpirationDateSignedDateOwnerorOwner'sdesignee,Title19CERTIFICATEOFINSERVICEINSPECTIONI,theundersigned,holdingavalidcommissionissuedbytheNationalBoardofBoilerandPressureYessetInspectorsandthoStateorProvinceofandemployedbyofhaveinspectedthocomponentsdescribedinRepair/ReplacementPlanNo.duringtheperiodto~andstatethattothobestofmyknowledgeandbelief,theOwnerhasperformedalltheactivitiesdescribedfnthoRepair/ReplacementPlaninaccordancewiththerequirementsofSectionXI.BysigningthiscertificateneithertheInspectornorhisemployermakesanywarranty,expressedorimptied,concerningtheactivitiesdescribedintheRepair/ReplacementPlan.Furthermore,neitherthoInspectornorhisemployershallboliableinanymannerforanypersonalinjuryorpropertydamageorlossofanykindarisingfromorconnectedwiththisinspection.Inspector'sSignatureCommissionsNationalBoard,State,Province,andEndorsementsDate19File:NMP1PP10.WPD

hIVNIAGARAalfMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTSAPPENDIXA-CLASS1SUMMARYTABLESTableofContentsRecordofRevisionASMECODECLASS1SECTIONXISUMMARYTABLESExaminationCategoryB-AExaminationCategoryB-DExaminationCategoryB-EExaminationCategoryB-FExaminationCategoryB-G-1ExaminationCategoryB-G-2ExaminationCategoryB-JExaminationCategory8-K.ExaminationCategoryB-L-1,B-L-2ExaminationCategoryB-M-1,B-M-2ExaminationCategoryB-N-1,B-N-2.B-N-3ExaminationCategoryB-0A-1A-2A-32-56-67-910-1415-1718-2122-2425-2627-2930-3233-33File:APPENDIXA.WPD

ElYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999,':'::.",':".."":;;:":::.':,"'".'2.'-.":;;"",",;..."RECORD'OFREVISION"';:,'.-".';:.:..'.;"'".:,',:.:-",;:;'EVISION>0,--.,~-.:-DATE-.:-:<<;-<<September27,1999AFFECTEDEntireDocument,REASON'FOR;REVISION"UpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:APPENDIXA.WPD

YNlAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ASMECODECLASS1SUMMARYTABLESFile:APPENDIXA.WPD

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:1CODEEDITION:E89PRESSURERETAININGWELDSINREACTORVESSELASMESECXIEXAMSYSTEMiTEN((ITEMDESCRIPTIONMETHODDESCRI('TlvNNO.OFCOMPONENTS(JOFNO.SCHEDULED/COHPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSBl.llCIRCUMFERENTIALSHEL(WELDSVOLUMETRICReactorVesselWelds4000000.0%0.0%00AllWelds,100%p0((weldlength,DeferralpermissibleBl.12LONGITUDINALSHELLWELDSVOLUMETRICReactorVesselWelds1212000.0'100120AllWelds,100%ppglpppgweldlength,deferralpermissible.Bl.21CIRCUMFERENTIALHEADWELDSVOLUMETRICReactorVesselWelds33001020Access.lengthofp0$333QlpppgAllwelds,lppiweldlength,Deferralpermissible.HER1DIONALHEADWELDS/VOLUHFTRICR~a"t~tVseel~~602G140AccessiblelengthofAllweids,)00%weldlength,Deferralpermissible.Bl.30SHELL-TO-FLANGEWELDVOLUMETRICReactorVesselWelds221050.0%00101008ofweld5ppglpppilength,PartialDeferralPermissableSeefootnote(3)and(4)~Bl.40HEAD-TO-FLANGEWELDVOLUMETRICReactorVesselSURFACE13101010100%ofweld333$666glpppglength,PartialDeferralPermissableseefootnote3.Bl.b!REPAIRWELDS>>BELTL(NEREGION;ATElvRYTvrAL:4((.8v4030019.0i8.5'41G0.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:2CODEEDITION:E89FULLPENETRATIONWELDSOFNOZZLESINVESSELSASMESECXIEXAMSYSTEMITEMiiITEMDESCRIPTIONMETHODDESCRIPTIONNO.OFCOMPONENTSllOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOMMENTSB3.100REACTORVESSEL-NOZZLEINSIDERADIUSSECTIONVOLUMETRICControlRodDrive11100000AllNozzles,25iipppiilppp,lpppqto50%1stperiod,RemainderbyendofIntervalVOLUHETRICEmergencyCondenserSupply22100010AllNozzles,25850.0%50.0%100.0%to50%1stperiod,RemainderbyendofIntervalVvLUME1ii1i.'evows<.:."ysavni0.01u00AllNozzles,25ippiiIpp.piitoSpn1stperiod,RemainderbyendofIntervalVOLUHETRICMainSteamSystem22100010AllNozzles,25050.0%50.0%100.05to50~1stperiodRemainderbyendofIntervalVOLUMETRICReact.urCoreSpray101000AllNozzles,25%50.0'h100.0%100.0%to50~1stperiodRemainderbyendofIntervalVOLUHETRICReactorHeadVent001000AllNozzles,25%ppaIpp.pgIpp.pgto50%1stperiodiRemainderbyendofIntervalVOLUHETRI(Rea-titinstrumentation0.0%00i0AllNozzles,251p.plilpp.pato50%1stperiod,RemainderbyendofIntervalVOLUHETRICReactorRecirculationDischarge55102020AllNozzles,25%20.0ii60.0li100.0%to50%1stperiod,RemainderbyendofIntervalVOLUMETRICReactorRecir~u'tlairSuction55201020AllNozzles,25%6ppqlpppiito50%1stperiod,Remainderbyend 0

DATE:10/26/99REVISION:00tkINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:3CODEEDITION:E89FUILPENETRATIONWELDSOFNOZZLESINVESSELSASMESECXIITEM(tITEMDESCRIPTIONB3.100EXAMMETHODSYSTEHDESCRIPTIONNO.OFCOMPONENTSttOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOHMENTSofIntervalVOLUHETRICReactorVesselNozzles1717505070AllNozzles,258294$588()lppp(tto50()1stperiod/RemainderbyendofIntervalITEMTOTAL:404012010018030.0055.0(t100.0tB3.I!0PRESSURIZER-NOZZLE-TO-VESSELWELDSN/APRESSURIZER-NOZZLEINSIDERADIUSSECTIONB3.130STEANGENERATORS(PRIMARYSIDE)-NOZZLE-TO-VESSELWELDS40STEAHGENERATORS(PRIHARYSIDE)-NOZZLEINSIDERADIUSSECTIONB3.90REACTORVESSEL-NOZZLE-TO-VESSELWELDSVOLUMETRICControlRodDrive11100000AllNozzles,25%lppp(tlppp(tlpp0()to50%1stperiodRemainderbyendofIntervalVOLUMETRICEmergencyCondenserSupply221050.0t0010AllNozzles,2545pp(tlppp(tto50%1stPeriod,RemainderbyendofInterval040AllNozzles,25%to50%1stperiod,Remainderbyendo!IntervalVOLUMETRICHainSteamSystem100010AllNozzles,25'45ppg5p0()lpp0()to50%1stperiod/RemainderbyendofIntervalVOLUMETRICReactorCoreSpray22101000AllNozzles,25%50.0()100.0%100.0%to50~1stPer"odRemainderbyend

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUHMARYTABLEAPAGE:4CODEEDITION:E89FULLPENETRATIONWELDSOFNOZZLESINVESSELSASMESECXIITEMt)ITENDESCRIPTIONB3.90EXAMMETHODSYSTEMDESCRIPTIONNO.OFCOHPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSofIntervalVI>,.'HETRi'~"i<tlt~>>cVentI00I000AllNozzles,25%00(t100.0%100.0%to50%1stPeriod,RemainderbyendofIntervalVOLUMETRICReactorInstrumentation11000.0%0010AllNozzles,25(t0.0%100.0()to5051stperiod,RemainderbyendofIntervalVOLUHETRICReactorRecirculationDischarge55I02020AllNozzles,25%20.0(t60.0%100.0%toSOS1stperiod/RemainderbyendofIntervalVOLUMETRICReactorRecirculationSuction5520I020AllNozzles,25%4ppg6p0()lppp(tto50%1stperiod/RemainderbyendofIntervalVOLUHETR/i:R<<,s"t.".V<<ss<<.:75050t0AllNozzles,25%1000(itO50(t1stperiod,RemainderbyendofIntervalITEMTOTAL:404012010018030.0%55.0%100.0(iB3.150HEATEXCHANGERS(PRIHARYSIDE)-NOZZLE-TO-VESSELWELDSr83.160HEATEXCHANGERS(PRIMARYSIDE)-NOZZLEINSIDERADIUSSECTIONN/AN/AB3.10REACTORVESSEL-tiOZZLE-TO-VESSELWELDSN/AB3.20REACTORVESSEL-NOZZLEINSIDERADIUSSECTIONti/APRESSURIZER-NOZZLE-TO-VESSELWELDSBv.4ui'RESSURIZER-NOZZLEINSIDERADIUSSECTIVitNIA 0

DATE:10/26/99REVISIOH:00NIHEMZLEPOINTNUCLEARPLAHTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIOHXZSUMMARYPAGE:5CODEEDITION'89TABLEAFULLPENETRATIONWELDSOFNOZZLESZNVESSELS(INSPECTIONASMESECXIITEMIITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB3.50STEAMGENERATORS(PRIMARYSIDE)-NOZZLE-TO-VCSSELWELDSN/AB3.60STEAMGENERATORS(PRIMARYSIDE)-NOZZLEINSIDERADIUSSECTIONH/AB3.70HEATEXCHANGERS(PRIMARYSIDE)-NOZZLE-TO-VESSELNELDSB3.80HCATCXCHANGCRS(PRIMARYSIDE)-NOZZLEINSIDERADIUSSECTIOHN/ACATEGORYTOTAL:808024020036030.0(j55.0%100.0(j

DATE:10/"6/99REVISION:QQII.'NEH.'LF.r'OIIITliU::.EARI'LAN>'NITI:ISERVI..!I!ISIE'"Io!!P:.ANi>lR'."IIETH:RDINTERVAI.'.l>SS:Se:"OiIi~SUHMARYTABLEAPAGE:6CODEEDITION:E89PRESSURERETAININGPARTIALPENETRATIONWELDSINVESSELSASHESECXIITEH8ITEHDESCRIPTIONB4.10PARTIALPENETRATIONI4ELDSEXAMMETHODSYSTEHDESCRIPTIONNO.OFCOMPONENTSIOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOMMENTSB4.11VESSELNOZZLESN/AB4.12CONTROLRODDRIVENOZZLESVISUALReactorVesselNozzles11000010258ofnozzles,0.0%0.0%100.0%DeferralpermissibleB4.13INSTRUMENTATIONNOZZLESVISUALReactorVesselNozzles1100001025%ofnozzles,Q.QI,Q.QII100.0IIpermissible~~'I~I'hI;SSI!8,1"ER-IIEATERI'ENETRATIONWELDS~I!CATEGORYTOTAL:220000200.010.0%100.00

DATE:10/26/99REVISION:00NINEHILEPOIttTNUCLEARPLANTUNIT1It)SERVICEINSPECTIONPLA!$FORTHETHIRDINTERVALCLASS1SECTIOttXISUMMARYTABLEAPAGE:CODEEDITION:E89PRESSURERETAININGDISSIMILARMETALWELDSASHESECXIITEMITENDESCRIPTIONEXAMMETHODSYSTEHDESCRIPTIONNO.OFCOHPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSREACTORVESSEL-NOZZLE-TO-SAFEENDBUTTWELDSNPS4orLARGERVOLUHETRICEmergencySURFACECondenserSupply22100010AllweldsMay00%500%100plcoincidewithCategoryB-DexaminationsVOLUMETRICReactorCoreSURFACESpray22101000AllweldsMay5p.pgIpp.pntlpppgcoincidewithCategory8-DexaminationsVOLUHETRICReactorHeadSURFACEVent001000AllweldsHayO.pit100.0't100.0%CategoryB-DexaminationsVOLUMETRICRe~cV>rSURFAL1nstiwill")~L.i<n-uI11vvuv10AllweldsHay0.0%100.0%coincidewithCategory8-DexaminationsVOLUMETRICReactorSURFACERecirculationDischarge55102020AllweldsMay2ppg6ppttlpp01,coincidewithCategoryB-DexaminationsVOLUMETRICReactorSURFACERecirculationSuction55201020AllweldsMayqppg6p01,lpppttcoincidewithCategoryB-DexaminationsVOLUMETRICReactorVessel17SURFACENozzles17605060AllweldsMay352$647glpp0~coincidewithCategoryB-DexaminationsL~I,J'L~33.a'~63.6t100.0%B'..10vHEATEXCHANGERS-NOZZLE-T<)-SAFEENDBUTTWELDS,NPSorLARGERN/AB5.110HEATEXCHANGERS-NOZZLE-TO-SAFEENDBUTTWELDSLESSN/A

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUtJIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:8CODEEDITION:E89PRESSURERETAININGDISSIMILARMETALWELDSASMESECXIITEMliITEMDESCRIPTIONB5.110THANNPS4EXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSttOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB5.120HEATEXCHANGERS-ttOZZLE-TO-SAFEENDSOCKETWELDSB5.130PIPING-DISSIMILARMETALBUTTWELDS,NPS4LARGERB5.140PIPING-DISSIMILARMETALBUTTWELDS,LESSTHAttNPS4B5.150PIPING-DISSIMILARMETALSOCKETWELDSB5.20REACTORVESSEL-NOZZLE-TO-SAFEENDBUTTWELDS,LESSTHANNPS4SURFACEControlRodDrive11100000AllweldsMaylppp%lppp%lppp%coincidewithCategoryB-DexaminationsSURFACELiquidPoison11100000AllweldsMaylppp%lppp%lppp%coincidewithCategoryB-DexaminationsSURFACEReactort~~~0~0%0020AllweldsMay100p%coincidewithCategoryB-DexaminationsITEMTOTAL:4420002050.0%50.0%100.0%B5.30REACTORVESSEL-NOZZLE-TO-SAFEENDSOCKETWELDSN/AB5.40PRESSURIZER-NOZZLE-TO-SAFEENDBUTTWELDS,NPS4orLARGERN/AB5.50PRESSURIZER-NOZZLE-TO-SAFEENDBUTTWELDSLESSTHANNPS4N/APRESSURIZER-NOZZLE-TO-SAFEENDSOCKETWELDS

DATE:10/26/99REVIS!OH:00NINEMILEPOINTNUCLEARPLANTUNIT1IHSERVICE1HSPECT)OHPLAHfORTHETHIRDINTERVALCLASS!Sf.('T!OHi'ISUMMARYTABLEAPAGE:9CODEEDITION:E89PRESSURERETAININGDISSIMILARMETALWELDSASMESECXIITEM5ITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSIOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCCMMENTSB5.70STEAMGENERATOR-NOZZLE-TO-SAFEENDBUTTWELDS,NPS4orLARGERN/AB5.80STEAMGENERATOR-NOZZLE-TO-SAFEENDBUTTWELDS,LESSTHANNPS4N/AB5.9vSTEAMGENERATOR-NOZZLE-TO-SAi'EENDSOCWETWELDSN/ACATEGORYTOTAL:3l3713010014035.1'162.1t100.0S

DATE:10/26/99REVISIOH:00NINEMILEPOINTNUCLEARPLANTUHIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYATABLEPRESSURERETAININGBOLTINGGREATERTHAN2INCHESINPAGE:10CODEEDITION:E89ASMESECXIITEMIITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OfCOMPONENTSOfttp.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB6.10REACTORVESSEL-CLOSUREHEADNUTSVISUALClosureHeadNuts6464220210210Allnuts34.3%67.1%100.0tB6.100STEAMGENERATORS-FLANGESURFACE,WHENCONNECTIONDISASSEMBLEDN/AB6.110STEAMGENERATORS-NUTS,BUSHINGS'NDWASHERSB6.120HEATEXCHANGERS"BOLTSANDSTUDSN/AB6.130HEATEXCHAHGERS-FLANGESURFACE,WHENCOHNECTIONDISASSEMBLEDN/AKe14>>HEATEXCttANGERS-NUTS,BUSHINGS'ttDWASHERSPIPING-BOLTSANDST'."'."PIPING-FLANGESURfACE,WHENCONNECTIOHDISASSEMBLEDtt<A86.170PIPING-NUTS,BUSHINGS,ANDWASHERSB6.180PUMPS-BOLTSANDSTUDSVOLUMETRICReactorRecirculationPump11001000Allbolts4studsppglpppttlpppttLimittocompsched.byCat.B-L-2VOLUMETRICReactorRecirculationPump12100000O.OS0.0%00Allbolts4studsppgLimittocompsched.byCat.B-L-2VOLUMETRICReactorp<>ml100000>>.Osv.p>>00Allbolts4studs0pgLimittocompsched.byCat.B-L-2VOLUMETRICReact.>RecirculationPump140'000O.OS0.0%00Allbolts4studsppgLimittocompsched.byCat.B-L-2

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUHHARYATABLEPRESSURERETAININGBOLTINGGREATERTHAN2INCHESINPAGE:11CODEEDITION:E89ASMESECXIITEMrrITEMDESCRIPTIONEXAMHETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSlfOFNO.SCHEDULED/COHPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVOLUMETRICReactorRecirculationPump15000000.00o.orr00AllboltsastudsppgLimittocompsched.byCat.8-L-2ITEMTOTAL:510010000.0%100.0%100.0%B6.190PUMPS-FLANGESURFACE,WHENCONNECTIONDISASSEMBLEDVISUALReactorRecirculationPump1111001000Allflangesurf.,0pqlpppqlppprrLimittocompsched.byCat.B-L-2VISUALReactorRecirculationPump121000000.OS0.0%00Allflangesurf.,ppgLimittocompsched.byCat.B-L-2VISUALReactorRecirculationPump131000000.08O.OS00Allflangesurf.,ppgLimittocompsched.byCat,B-L-2VISUALReactorRecirculationPump141000000.0'10.Orr00Allflangesurf.,ppgLimittocompsched.byCat.B-L-2VISUALReactorRecirculationPump151000~000.0't0.0'rr00Allflangesurf.,ppgLimittocompsched.byCat.B-L-2ITEMTOTAL:510010000.0%100'%100.0%B6.20REACTORVESSEI-CLOSURESTUDS,INPLACEVOLUMETRICClosureHeadSURFACEStuds6464220210210Allstuds34.3%67.1%100.0%Ba<<PVPUMPS"NUTS,BUSHINGS,ANDWASHERSVISUALReactor.Re~!rrculati.rPump11003000Allnuts,bush.pylppprtlpppgMashLimittocompsched.byCat.B-L-2 0

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMHARYATABLEPRESSURERETAININGBOLTINGGREATERTHAN2INCHESINPAGE:12CODEEDITION:E89ASMESECXIITENIITEMDESCRIPTIONEXAMMETHODSYSTEHDESCRIPTIONNO.OFCCHPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVISUALReactor300000Recirculation0.0%0.0%Pump1200Allnuts,bush.ap0%washLimit.tocompsched.byCat.B-L-2VISUALReactorRecirculationPump133000000.0%0.0%00Allnuts,bush.app%washLimittocompsched.byCat.B-L-2VISUALReactorRecirculationPump14u00000.0'%.0'%0Allnuts,bush.Spp%washLimittocompsched.byCat.B-L-2VISUALReactorRecirculationPump153000000.0%0.0%00Allnuts,bush.app%washLimittocompsched.byCat.B-L-2ITEMTOTAL:1530030000.0%100.0%100.0%B6.210VALVES-BOLTSANDSTUDSVOLUHETRICFeedwaterSystem21001000Allboltsandpp%lppp%lppp%studs,LimitedtocomponentsselectedunderCategoryB-M-2,VOLUHETR1CRe."~ii11v0000Allboltsand>>>u0%lppp%studs,LimitedtocomponentsselectedunderCategoryB-M-2,VOLUHETRICReactorShutdownCooling0.0%pp%lppp%studs,LimitedtocomponentsselectedunderCategoryB-H-2,11000010AllboltsandITEMTOTAL:5310101033.3%66.6%100.0%

DATE:lp/26/99REVISION:00NINEMZLEPOINTNUCLEARPLANTUNIT1ZNSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUHHARYTABLEAPAGE:13CODEEDITION:E89PRESSURERETAININGBOLTINGGREATERTHAN2INCHESINASHESECXIITEHITEMDESCRIPTIONEXAMHETHODSYSTEMDESCRIPTIONNO.OFCOHPONENTSOFWO.SCHEDULED/COMPLETEDCOMPRE@1STPER2NDPER3RDPERCOMMENTSB6.220VALVES-FLANGESURFACE,NHENCONNECTIONDISASSEMBLEDVISUALFeedwaterSystem21001000Allflange0.0%100.08100.08tovalveselectedunderCategoryB-M-2VZSUALReactorCoreSpray21100'00AllflangelpppglpppqlpppIIsurfaces,LimitedtovalveselectedunderCategoryB-H-2VISUALReactorShutdownCooling11000.0%0010Allflangep0IIlpp0IIsurfaces,LimitedtovalveselectedunderCategory8-H-2ITCHTOTAL:5310101033.3166.6%100.0%B6.230VALVES-NUTS,BUSHINGS,ANDNASHERSVISUALFeedwaterSystem1001000Allnuts,ppqlpp0IIlpppgbushings,washers,LimitedtovalveselectedunderB-M-2VISUALReactorCoreSpray63300000Allnuts,Ipp.0IIlpppI,lppplIbushings,washers,LimitedtovalveselectedunderB-M-2VISUALReactorShutdownCoolingI1000.0%0010Allnuts,ppglpppgbushings,washers,LimitedtovalveselectedunderB-H-2ITEMTOTAL:9530101060.0't80.08100.0%STUDS,WHENREMOVEDStudsREACTORVESSEL-CLOSURESURFACEGlosureHead1310101012studs,Deferraly3y$666'pp01Permissable,RG1.26,C.2.b.,a

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYATABLEPRESSURERETAININGBOLTINGGREATERTHAN2INCHESZNPAGE:14CODEEDITION:E89ASMESECXIITEMiITEMDESCRIPTIONB6.30EXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSIOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSminimumof4perperiodB6.40REACTORVESSEL-THREADSINFLANGEVOLUMETRICReactorVesselFlange6464220210210Allthreadsin343$671$lpppgflange,B6.50REACTORVESSEL-CLOSUREVISUALClosureHeadWASHERS,BUSHINGSWashers128128440420420Allwashers4343tj67IttIpppgBushingsVISUALReactorVessel6464220210210Allwashers4Flange34.3tt67.1tt100.0ttBushingsITEMTOTAL:19219266063063034.3tt67.18100.0ttPRESSURIZER-BOLTSANDSTUDSPRESSURIZER-FLANGESURFACE,WHENCONNECTIONDISASSEMBLEDPRESSURIZER-t<UTS,BUSHINGS,ANDWASHERtlatABB.00STEAMGENERATORS-BOLTSANDSTUDStilACATEGORYTOTAL:42940313801350130034.2%67.7'0100.0tt

DATE:10/26/99REVISIONr00NINEMILEPOlNTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYBLEATh2-PRESSURERETAININGBOLTING,2INCHESANDLESSINPAGE:15CODEEDITION:E89ASMESECXIITEMNO.OFCOMPONENTSEXAMSYSTEMIIOFNO.SCHEDULED/COMPLETEDITEMDESCRIPTIONMETHODDESCRIPTIONCOMPREQ1STPER2NDPER3RDPERCOMMENTS87.10REACTORVESSEL-BOLTS,STUDS,ANDNUTSVISUALReactorVessel1818505080hllbolts,studsNozzles27.7rt55.5%100.0%87.20PRESSURIZER-BOLTS'TUDS,ANDNUTS87.30STEAMGENERATORS-BOLTS,STUDS,ANDNUTSHEATEXCHANGERS-BOLTS,STUDS,ANDNUTSN/hsr5rP!PING-BOLTS,STUDS,A"'"O'SUA'UTSHen"00000hllbolts,studs>Pe.u'tluuv'0100.0'4andnuts,Limitedto8-JVISUALReactorRecirculationDischarge55202010Allbolts,studs4ppgSp.pgIpp.pgandnuts,Limitedto8-JVISUALReactorRecirculationSuction55003020Allbolts,studsO.pt60.00100.0%andnuts,Limitedto8-JITEMTOTAL:121240503033.3rr75.0t100.0887.6UPUMPS-BOLTS,STUDS,ANDNUTSVISUALReactorRecirculationPump1111001000hllbolts,studspprrlppprrlppprrandnuts,Limitedto8-L-2ViSUALn~cl%'r,"A,Recflr'ouisr.r'>Pulap0nv00u0Allbolts,stud's00~ppq0pgandnuts,Limitedto8-L-2VISUALReactorRecirculationPump1310000000Allbolts,studsppgppgppqandnuts,Limitedto8-L-2VISUALReactorRecirculationPump1410000000Allbolts,studspgppgppqandnuts,Limitedto8-L-2

DATE:10/26/99REVISION:00ttlNENILEPC>!ttTtlUCLEARPL%'<TUttIT1INSERVICEINSPECTtr>ttPltutFORTHETHIRDINTERVALCLASS1SECT10ttXISUMMARYPAGE:16CODEEDITION:E89TABLEAPRESSURERETAININGBOITING,2INCHESANDLESSINASMESECXIITEMttITEHDESCRIPTIONBt.60EXAMMETHODSYSTEMDESCRIPTIONReactorRecirculationPump15ITEMTOTAL:NO.OFCOHPONENTSttOF'O.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPER51001000O.OF>100.0%100.0%COHMENTSAllbolts,studsandnuts,Limitedto8-L-2B770VALVESBOLTS>STUDS>ANDVISUALNUTSControlRodDrive33100020Allbolts,studs333$333>1lpppF>andnuts,LimitedtoB-M-2VISUALEmergencyCondenserReturn63201000Allbolts,studs66.6t100.0%Ipp.pirandnuts,LimitedtoB-M-2VISUALE>r>v>ge>>.y>or>censerSupplyv000000Allbolts,studspptt0pippgandnuts,LimitedtoB-M-2VISUALFeedwaterSystem21100000Allbolts,studs100.0%100.pttIpp.0>tandnuts,LimitedtoB-H-2VISUALl.iquidPoison22101000Allbolts,studs5pptt1pppt>1pppttandnuts,LimitedtoB"H-2VISUALHainSteamSystem174004000Allbolts,studsp.prtlpppglpppgandnuts,LimitedtoB-M-2VISUALReactorCleanUp41001000Allbolts,studsp.pg100.0>tIpp.pqandnuts,LirritedtoB-H-2VISUALkea"r~r""><:Sprayl.5"0I020Allbolts,studs0.0'tGp.pt100.0%andnuts,Limitedto8-H-2VISUALReactorDrain4002020Allbolts,studsp.ptt5ppttlpppttandnuts,Limitedto8-M-2

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYBLEATAPRESSURERETAININGBOLTING,2ZNCHESANDLESSINPAGE:17CODEEDITION:E89ASMESECXIITEMiiITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVISUALReactorHead33300000Allbolts,studsVentlpppilpppqlpppqandnuts,LimitedtoB-M-2VISUALReactorRecirculationDischarge105102020Allbolts,studs20Oh60OS100.0%andnuts,LimitedtoB-M-2VISUALReactorRecirculationSuction51001000Allbolts,studsppqlpppglpppgandnuts,LimitedtoB-M-2VISUALReactorShutdown31000010Allbolts,studsCoolingppgppt,lpppgandnuts,LimitedtoB-M-2ITEMTOTAL:75331101309033.3%72.7%100.0SB78(>>CRDHOUSINGSBOLTS'TUDS,ANDNUTSVISUALControlRodDriveHousings1364102010Allbolts,studs250$75pglpppiiandnuts,whenCRDdisassembled'ATEUt>R':T(.'AL:.'466t'10602103v.8'a69.1'4100.0%

DATE:10/26/99REVISION:00NINEHILEPO1NTttUCLEARPLANTUNIT1INSERVICEIttSPECTIOttPLANFORTHETHIRDIttTERVALCLASS1SECTIONXISUHMARYTABLEAPAGE:18CODEEDITION:E89PRESSURERETAININGWELDSINPIPINGASHESECXIITEMITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCCHPREQ1STPER2NDPER3RDPERCOMMENTSB9.11CIRCUMFERENTIALPIPEWELDS,NPS4orLARGERVOLUMETRICEmergency320000000Atleast25ttofCondenserReturnO.pit0.0%O.ptttheweldsVOLUHETRICEmergencySURFACE,~,ndensorSupply165500000Atleast25ttofIpp.piIpp.pi'pp.pgtheweldsVOLUMETRICFeedwaterSystem50120010110Atleast25%ofSURFACEppg83ttlppptttheweldsVOLUMETRICMainSteamSURFACESystem3411201080Atleast25'Iof18.1%27.21100.00VOLUMETRICReactorCleanUp3011003080Atleast25%ofSURFACEO.ptt27.24100.05theweldsVOLUMETRICReactorCoreSURFACESpray706302010Atleast25%of50.0%83.3$100.penttheweldsVOLUHETRICReactorRecirculationDischarge4317504080Atleast25%of29.4'2.9tt100.0lttheweldsVOLUMETRICReactorSURFACEt<ecltrulelntufI~<<g5419408070Atleast258of1ppptttheweldsVOLUt4ETRICReactorShutdown163101010Atleast254ofCooling33.3'6.6%100.0%theweldsITCHTOTALt3458420020044023.8147.6%100.0lB9.12LONGITUDINALPIPEWELDS,VOLUHETRICEmergencyNPS4orLARGERCondenserReturn47000000.0%O.OS00Onepipediameter,ppttor12inchesofeachweldselectedunderCategoriesB-FandB-J,CodeCaseN-524VOLUMETRICReactorCoreSURFACESpray550000000OnepipediameterO.pttppttppttor12inchesofeachweldselected

DATE:10/26/99REVI8IvH:00ttlttF.HlI.EI'OtttTt!U.LEAFPLAttTUttliI!ttSERVICF,IttSI'E-,TIARA!I".hl':-"i)k'!'HFTHIRDIt'TRVALCI>>ASSISE-lr)llXlSUMHARYTABLEAPAGE:19CODEEDITION:E89PRESSURERETAININGWELDSINPIPINGASMESECXIITEHttITEMDESCRIPTIONB9.12EXAMHETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSttOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOHMENTSunderCategoriesB-FandB-J,CodeCaseN-524VOLUMETRICReactorRecirculationDischarge7818505080Onepipediameter27.7%55.5%100.0%or12inchesofeachweldselectedunderCategoriesB-FandB-J,CodeCaseN-524VOLUHETRICReactorSURFACERecirculationSuction83264013090Onepipediameter153%653%lppp%or12inchesofeachweldselectedunderCategoriesB-FandB-J,CodeCaseN-524VOLUHETR!CReaorutShutdewn5"00"000OnepipediameterCoolIng0.0%100.0%100.0%or12inchesofeachweldselectedunderCategoriesB-FandB-J,CodeCaseN-524ITEHTOTAL:288469020017019.5%63.0%100.0%B9.21CIRCUMFERENTIALPIPE!4ELDS>>LESSTHANNPS4SURFACEControlRodDrive208700010Atleast25%of7.5%87,5%lpQ.Q%theweldsSURFACELiquidPoison205400010Atleast25%of80.0%80.0%100.0%SURFACEHainSteamSystem144201010Atleast25%of5Q0%75.p%Ippp%thewelds.::!HFA'Et\~'>>>>'.I~s3050Atleast25%ofiQ.0%IOP.O%sURFAcEReactorDrain121001000Atleast25%ofpp%lppp%lppp%thewelds

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:20CODEEDITION:E89PRESSURERETAININGNELDSINPIPINGASMESECXIITEMllITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OF'OMPONENTSllOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSSURFACEReactorHead114400000Atleast25%ofVent100.0%100.0%100.0%SURFACEReactorInstrumentation5"000020Atleast25%cfp.p%pp%lpp.p%theweldsSURFACEReactorInstrumentstion10000000Atleast25%ofp0%pp%pp%theweldsSURFACEReactorRecirculationDischarge305000050Atleast25%of0.0%0.0%100.0%theweldsSURFACEReactorRecirculationSuction21000010htleast25%ofpp%pp%lppp%thewelds!TEMTOTAL:164l42305016052.2%63.6%100.0%B9.'"LONGITUDINALPIPEWELDS,LESSTHANNPS4N/AB9.3)BRANCHCONNECTIONWELDS,VOLUMETRICMainSteamNPS4orLARGERSURF'ACESystem62200000Atleast25%of1000%1000%1000%theweldsVOLUMETRICReactorCoreSURF'ACESpray20000000htleast25%of00%00%00%theweldsVOLUMETRICReactorSURFACERecirculationSuction1001000Atleast25%ofpp%lppp%lppp%theweldsITEMTOTAL:9320100066.6%100.0%100.0%B4.4'RANCHCONNECTIONWELDS,SURFACEMainSL,eaa(1001000Atleast,25%LESSTHANNPS4Sysl~'ml0.0%100.0%100.0%SURFACEReact.ovCLeanUp1110v000htleast25%100.0%100.0%100.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUYAARYTABLEAPAGE:21CODEEDITION:E89PRESSURERETAININGWELDSINPIPINGASHESECXIITEHFITEHDESCRIPTIONEXAHHETHODSYSTEHDESCRIPTIONNO.OF'CHPONENTSOf'O.SCHEDULED/CCHPLETEDCOHPREQ1STPER2NDPER3RDPERCOHHENTSSURFACEReactorCore41001000Atleast25%Spray0.0%100.0%100.0%SURF'ACEReactorRecirculationDischar9e102101000Atleast25%50.0%100.0%100.0%;UKFACF.ke~ctkeelrcuiatioitSuction00!010Atleast25%0.0%50.0%100.0'%TEHTOTAL:26720401028.5%85.7%100.0%B9.40SOCKETNELDSSURFACEHainSteamSystem91001000Atleast25%ofpp%lppp%lppp%theweldsSURFACEReactorDrain105002030Atleast25%ofpp%4p0%lppp%theweldsSURFACEReactorHeadVent144400000Atleast25%oflppp%lppp%lppp%theweldsSURFACEReactorInstrumentation61000010Atleast25%ofpp%lppp%thewelds.NtlkFA'.r.kt'"tIy~~tDisabhar:t-s~tt~0'u50Atleast25%ofwe1dsITEHTOTAL:692040709020.0%55.0%100.0%CATEGORYTOTAL:90120460057087029.4%57.3%100.0%

0 DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1IHSERVICEINSPECTIOHPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:22CODEEDITION:E89INTEGRALATTACHMENTSFORPZPZNG,PUMPS,ANDVALVESASMESECXlITEMNITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2HDPER3RDPERCOMMEHTSBlp.20PIPING-ZNTEGRALLYWELDEDSURFACEATTACHMENTSControlRodDrive0.0%0.0%ppgattachmentsofpipingrequiredunderCategoryB-J,CodeCaseN-5091000000010%ofallWeldedSURFACEEmergencyCondenserReturn10220000010%ofallWeldedlpppqlpppglpppgattachmentsofpipingrequiredunderCategoryB-J,CodeCaseN-509SURFACEFeedwaterSystem184000.0%004010'1ofallWeldedppilppptattachmentsofpipingrequiredunderCategoryB-J,CodeCaseH-509SURFACEMainSteamSystem16400400010%ofallWeldedppglpppqlpppgattachmentsofpipingrequiredunderCategoryB-J,CodeCaseN-509SURFACEReactorCleanUp232002000108ofallWelded0pglpppglpppqattachmentsofpipingrequiredunderCategoryB-J,CodeCaseH-509SURFACEReactorCoreSpray344000.0'8004010%ofallWeldedppglpppgattachmentsofpipingrequiredunderCategoryB-J,CodeCaseN"509SURFACEReactorDrain000000010%ofallWeldedppgppgppgattachmentsof

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXlSUMMARYBLEATAINTEGRALATTACHMENTSFORPIPING,PUMPS,ANDVALVESPAGE:23CODEEDITION:E89ASMESiU'::iITEM0ITEMDESCRIPTIONB10.20NO.OFCOMPONENTSEXAMSISTEMOFNO.SCHEDULED/COMPLETEDMETHOD:lES:RiPTIONC(44iREQ1STPERNDPER3RDPERCOMMENTSpipingrequiredunderCategoryB-J,CodeCaseN-509SURFACEReactorRecirculationDischarge24440000010%ofallWelded100.0%100.0%100.0%attachmentsofpipingrequiredunderCategoryB-J,CodeCaseN-509SURFACEReactorRecirculationSuction204000.0%004010%ofallWeldedp0%lppp%attachmentsofpipingrequiredunderCategoryB-J,CodeCaseN-509SURFACEfee~it.'.huorwn5000Coi~~~lq000010%ofallWeldedpp%attachmentsofpipingrequiredunderCategoryB-J,CodeCaseN"509ITEMTOTAL:15524606012025.0%50.0%100.0%B10.30PUMPS-INTEGRALLYWELDEDATTACHMENTSN/ABl0.40VALVES-INTEGRALLYWELDEDSURFACEControlRodATTACHMENTSDrive00100010%ofallWelded0.0%100.0%100.0%attachmentsofvalvesrequiredunderCategoryB-J,CodeCaseN-509SURFACELiquidPoison1000000010%ofallWeldedpp%pp%pp%attachmentsofvalvesrequiedunderCategoryB-J,CodeCaseN-509

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANfORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYBLEATAINTEGRALATTACHMENTSFORPIPING,PUMPS,ANDVALVESPAGE:24CODEEDITION:E89ASHESECXIITEMllITEMDESCRIPTIONBlp.40EXAMHETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSIIOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOMMENTS10%ofallWeldedattachmentsofvalvesrequiredunderCategoryB-J,CodeCaseN-509SURfACEReactorCoreSpray2000000.0%0.0'll0010%ofallWeldedppgattachmentsofvalvesrequiredunderCategoryB-J,CodeCaseN-509SURFACEReactorShutdown2100Cooling0.0%0010lpllofallWeldedppglpppgattachmentsofvalvesrequiredunderCategoryB-J,CodeCaseN-509'ITEHTOTAL:830010200.0%33.3ll100.0'1Blp.10PRESSUREVESSEL-INTEGRALLYWELDEDATTACHHENTSSURFACEReactorVesselSupp'ts63101010100%ofthelength333%666%1000%oftheweldstothevessel.CodeCaseN-509CATEGORYTOTAL:16930708015023.3%50.08100.0%

DATE:1v/"6/99REVISION:00tt1NF.MILLPvttt't'UCLEARPLANTUttIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIOltXISUMMARYTABLEAPAGE:25CODEEDITION:E89PRESSURERETAININGNELDSINPUMPCASINGASMESECXIITEMIITEMDESCRIPTIONB12.10PUMPS-PUMPCASINGWELDSEXAMMETHODNO.OFCOMPONENTSSYSTEM8OFNO.SCHEDULED/COMPLETEDDESCRIPTIONCOMPREQ1STPER2NDPER3RDPERN/ACOMMENTSCATEGORYTOTAL:000000000.0%0.OtalO.OS

DATE:10/26/99REVISION:00NINENILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:26CODEEDITION:E892-PUMPCASINOSASMESECXI'.TFMttITEMDESCRIPTIOttEXAMNETHr>!.'YSTEMDESCR!PTIOttNO.OFCOMPONENTSIOF'O.SCHEDULED/COMPLETEDCrgt['EQ1STPER2NDPER3RDPERCOMMENTSBl.20PUMPS-PUMPCASINGSVISUALtK4th.'leet>'culaCionPur<<p1110.01000Onepump,whenp.pttIpp.pttlpppttdisassembledformaint.VISUALReactorRecirculationPump1210000000Onepump,when00%0pttppgdisassembledformaint.VISUALReactorRecirculationPump1310000000Onepump,whenp.pgpp>tppttdisassembledformaint.VISUALReactor.RecirculationPump1410000000Onepump,whenp.pttppgp.pt>disassembledformaint.VISUALReactorRecirculationPump1510000000Onepump,whenppgppttppttdisassembledformaint.IFtt'r>T/>I.5)0010000.u't100.0>>100.0%CATEGORYTOTAL:51'010000.0%0.0%100.0%

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:27CODEEDITION:E89PRESSURERETAININGWELDSZNVALVEBODIESASMESECXIITEMIIITEMDESCRIPTIONB12.30VALVES-VALVEBODYWELDS,LESSTHANNPS4EXAMMETHODSYSTEMDESCRIPTIONN/ANO.OFCOMPONENTSIIOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOHMENTSBI2.40VALVES-VALVEBODYWFI,DS,VOLUMFTRI<HainSr~amNPS4orLARGERSr/sr.errr61001000Limitedtootle0.0'1100.0'00.0IIofvalvesCATEGORYTOTAL:61001000O.OII0.0%100.0II

DATE:)0/6/99REVISION:00iffsERvfcE:Nsf'F'T:tsf:"jvf=.>R.!lF'."!if!if"flfTERvAI.CLASS1SECTIONXfSUMMARYTABLEAPAGE:28CODEEDITION:E89VALVEBODIESASMESECXIITEMllITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOHPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB12.50VALVES-VALVEBODIESEXCEEDING4INCHESNOMINALPIPESIZEVISUALEmergencyCondenserReturn63201000Onevalveeach66.6tf100.0%100.0%groupofvalvesifdiss.formnt.reasonsDeferPermisVISUALEmergencyCondenserSupply0.0%0.0%100.0%groupofvalves!.fdiss.formnt.reasonsDeferPermis41000010OnevalveeachV!SUAl.In1000Onevalveeach5u.palpp.ui100.0%groupofvalvesifdiss.formnt.reasonsDeferPermisVISUALHainSteamSystem163003000Onevalveeach0.0%100.0!f100.0%groupofvalvesifdiss.formnt.reasonsDeferPermisVISUALReactorCleanUp42002000Onevalveeachpptllpppglppptlgroupofvalvesifdiss.formnt.reasonsDeferPermisVISUALReactorCoreSpray102200000Onevalveeachlpppilppptflpppggroupofvalvesifdiss.formnt.reasonsDeferPermisVISUALReactorRecirculationDischarge5000000.Off0.0%00Onevalveeachpptlgroupofva)vesifdiss.formnt.reasonsDeferPermisVISUALReactorRecirculation51001000Onevalveeachppglpppilppptfgroupofvalvesif

DATE:10/26/99R'=V:.t!UN:ptNINEMILEPOINTNUCLEARPLANTUt!IT1IIISERVICEINSPECTIOIIPLANFORTHETHIRDINTERVALi!ASS!SFcTIr>!I!ISUMMARYTABLEAPAGE:29CODEEDITIOtl:E89VALVEBODIESASMESECXIITEMllITEMDESCRIPTIONEXAMMETHODSYSTEHDESCRIPTIONNO.OFCOHPONENTSOF'O.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOMMENTSB12.50VISUALSuctionReactorShutdownCooling0.0%p01lpp01groupofvalvesifdiss.formnt.reasonsDeferPermisdiss.formnt.reasonsDeferPermis42000020OnevalveeachVISUALReactorVesselNor@les81100000OnevalveeachIpp.p!tIpp.pl!Ipp.p!tgroupof.valvesifdiss.formnt.reasonsDeferPermis:TEMTiiTAI.:66I>60803035.258.3'L100.0'1i'ATEGORYTUTAL:661760803035.2%82.3!t100.0S

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMHARYTABLEAPAGE:30CODEEDITION:E89ASMESECXIITEMINTERIOROPREACTORVESSELITEMDESCR1PTIONEXAMMETHODSYSTEHDESCRIPTIONNO.OFCOHPONENTSIIOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB13F10REACTORVESSEL-VESSELINTERIORVISUALReactorVessel3620Interior33.3%2020Firstrefuellpppgoutagethenonceeachinspectionperiod'A::4.>AYTOTAL:6002033.3%0.0'1100.0'h

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:31CODEEDITION:E892INTEGRALLYWELDEDCORESUPPORTSTRUCTUREASMESECXIITEM8ITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPRE{}1STPER2NDPER3RDPERCOMMENTSB13.40REACTORVESSEL(BWR)-CORESUPPORTSTRUCTUREVOLUMETRICReactorVesselInterior4961350120140AccessiblepglpppgsurfacesB13.20REACTORVESSEL(BWR)-INTERIORATTACHMENTSWITHINBELTl,INEREGIONVISUALReactorVesselInterior55102020AllweldsDeferral20.0%60.0%100.0%PermissableB)3.30REACTORVESSEL(BWR)-INTERIORATTACHMENTSBEYONDBELTLINEREGIONB13.50REACTORVESSEL(PWR)-INTERIORATTACHMENTSWITHINBELTLINEREGIONN/AREACTORVESSEL(PWR)-INTERIORATTACHMENTSBEYONDBELTLINEREGIONN/ACATEGORYTOTAL:546636014016054.5'175.7S100.0%

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIOff:;".SUMMARYTABLEAPAGE:32CODEEDITION:E893-REHOVABLECORESUPPORTSTRUCTURESASHESECY.IITEM8ITEHDESCRIPTIONBI3.70REACTORVESSEL(PWR)-CORESUPPORTSTRUCTUREEYAHMETHODSYSTEMDESCRIPTIONNO.OFCOMPOHENTSOF'O.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOHMENTSCATEGORYTOTAL:00000000O.OS0.0%0.0t

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:33CODEEDITION:E89-PRESSURERETAININGWZLDSINCONTROLRODHOUSINGSASMESECXlITEMliITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCCMPONENTStlOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSB14.10REACTORVESSEL-WELDSINSURFACEControlRod88203030108peripheralCRDCONTROLRODDRIVEDriveHousings25pg625glpppgHousings,DeferralHOUSINGSPermissableCATEGORYTOTAL:8820303025.080.0%100.0%

EIYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContentsRecordofRevisionTABLEOFCONTENTSAPPENDIXB-CLASS2SUMMARYTABLESB-1B-2ASMECodeClass2SectionXISummaryTablesExaminationCategoryC-AExaminationCategoryC-BExaminationCategoryC-CExaminationCategoryC-DExaminationCategoryC-F-1ExaminationCategoryC-F-2ExaminationCategoryC-G.B-334-3536-3738-3940-40..41-4142-4546-46File:APPENDIXB.WPD

ElVNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999RECORDOFREVISION'""REVISION;0,;:.",'..';."',GATE";;.".'September27,1999AFFECTEDPAGESEntireDocument>@REASONFORREVISION.UpdatedInserviceInspectionProgramPlanforthe3"'enYearInserviceInspectionIntervalFile:APPENDIXB.WPD

ElYNIAGARAH4MOHAWKNineMllePointNuclearPowerStationUnlt1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ASMECODECLASS2SUMMARYTABLESFile:APPENDIXB.WPD

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONXISUMMARYTABLEAPAGE:34CODEEDITION:E89PRESSURERETAZNZNGWELDSZNPRESSUREVESSELSASMESECXIITEM5ITEMDESCRIPTIONCl.lpSHELLCIRCUMFERENTIALWELDSEXAMMETHODNO.OFCOMPONENTSSYSTEMIOFNO.SCHEDULED/COMPLETEDDESCRIPTIONCOMPREQ1STPER2NDPER3RDPERCOMMENTSC1.20HEADCIRCUMFERENTIALWELDSN/AC1.30TUBESHEET-TO-SHELLWELDSVOLUMETRICEmergencyCondenserHeatExchanger11120000000LimitedtooneppgppgppgvesselinagroupofvesselsEx.'n~r>g>>:!1.u000LimitedtooneppgvesselinagroupofvesselsVOLUMETRICEmergencyCondenserHeatExchanger12120000000LimitedtooneppgppgppgvesselinagroupofvesselsVOLUMETRICEmergencyCondenserHeatExchanger12222101000Limitedtoone5ppglpppglpppgvesseli.nagroupofvesselsVOLUMETRICReactorContainmentSprayHeatExchangerill20000000LimitedtooneppgppgppgvesselinagroupofvesselsVOLUMBTRICReactorasr>air>>>>er>tSf,~'>'>"w(20000000Limitedtooneu0~pp~0pgvesselinagroupofvesselsVOLUMETRICReactorContainmentSprayHeatExchanger121v000000Limitedtooneppt,ppgppgvesselinagroupofvesselsVOLUMETRICReactorContainmentSprayHeatExchanger12222000020Limitedtoonepp>1ppalppp>1vesselinagroupofvesselsITEMTOTAL:16410102025.0050.0%100.0%

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUN1T1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMHARYTABLEBPAGE:35CODEEDITION:E89PRESSURERETAININGWELDSINPRESSUREVESSELSASMESECXIITENfiITEMDESCRIPTIONNO.OFCOHPONENTSEXAMSYSTEMIOFNO.SCHEDULED/COMPLETEDHETHODDESCRIPTIONCOMPREQ1STPER2NDPER3RDPERCOMMENTSCATEGORYTOTAL:16410102025.0%O.OS100.08

DATE:10/26/99REVISIONr00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYTABLEBPAGE:36CODEEDITION:E89PRESSURERETAININGNOZZLE%tELDSINVESSELSASMESECXIITEMsITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSttOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSNOZZLE-TO-SHELL(ORHEAD)WELD<~1/2Lli.NOMINALTHICKNESS<tRFACERr>~1"~Con%atlrmvlrkSprayHeatExtwanger111000000.0%0.0%00Allnozzlesatp0%TerminalEndsofpipingrunsselectedunderC-FSURFACEReactorContainmentSprayHeatExchanger1122000000.0%0.0%00Allnozzlesatpp%TerminalEndsofpipingrunsselectedunderC-FSURFACEReactor20000000A)1nozzlesatContainmentSprayHeatExchanger1210.0%0.0%pp%TerminalEndsofpipingrunsselectedunderC-FSURFACEReactorContainmentSprayHeatExchanger12222000.0%0020Allnozzlesatpp%lpp0%TerminalEndsofpipingrunsselectedunderC-F.'"Et)TrrTAL:00u.0%0020v.0%100.0%I~rttOZZLE-TO-SHELLtORftEAD)WELD>1/2Itt.NOMINALTHICKNESSWITHOUTREINFORCINGPLATEVOlUMETRI<t'iercCoridensrHeatExchanger1110.0%0000Allnozzlesatpp%pp%terminalendsofpipingrunsselectedunderCategoryC-F,LimitedtoonevesselVOLUMETRICEmergencySURFACECondenserHeatExchanger1120.0%0.0%0.0%terminalendsofpipingrunsselectedunderCategoryC-F,Limitedtoonevessel20000000AllnozzlesatVOLUMETRICEmergencyCondenserHeatu(a><u("200000P.0%0.0%00Allnozzlesatpp%terminalendsofpipingrunsselectedunderCategoryC-F,Limitedtoone

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLAttTUt)IT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYTABLEBPAGE:37CODEEDITION:E89PRESSURERETAININGNOZZLENELDSINVESSELSASMESECXIITEMff.ITEMDESCRIPTIOWC2.21'XAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSiOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSvesselVOLUMETRICEmergencySURFACECondenserHeatExchanger1222210'000AllnozzlesatSppglpppgIpp.pgterminalendsofpipingrunsselectedunderCategoryC-F,LimitedtoonevesselITEMTOTAL:82101000Su~Ob1008100'f)ttOZZLEIttSIDERADIUSSECTION>1/2IW.NOMINALTHICKNESSWITHOUTREINFORCINGPLATEW/AREINFORCINGPLATEWELDSTONOZZLEANDVESSEL)1/2IN.NOMIHALTHICKNESSN/AC2.32NOZZLE-TO-SHELLfORHEAD)WELDSWHENINSIDEOFVESSELISACCESSIBLE'i1/2IN.NOMINALTHICKNESSC"~33NOZZLE-TO-SHELL(ORHEAD)WELDSttHENINSIDEOFHELDISINACCESSIBLE1/2IN.NOM1NALTHICKNESSW/*CAEGURYTOTAL:16410102025.0t0.01100.0ft

DATE:10/26/99R.VIS!OH:00ll>NeM~>>.<<..;>>1>in>~>I.'ARt>l~tt~!NSERVICE!HSIEC'I'lr>Nil~NFORTNET!!IRD!tlTERVALC!rAcc.'ET!OtlXISUMMARYTABLE8PAGE:38CODEEDITION:E89INTEGRALATTACHMENTSFORVESSELS,PIPING,PUMPS,ANDASMESECXIITEMtlITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONHO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCCHPREQ1STPER2NDPER3RDPERCOMMENTSC3.10PRESSUREVESSELS-INTEGRALLYWELDEDATTACHMENTSSURFACEReactorContainmentSprayHeatExchanger1112000000010%ofAllppitppitppitattachments,CodeCaseN-509SURFACEReactorContainmentSprayHeatExchanger1122000000010%ofAll0.0%O.OI>O.OI>attachments,CodeCaseH-509SURFACEReact,orC>;><a!r>me<<r3pI>yI!i-'v(000000010%ofAll00~ppqppitattachments,CodeCaseH-509SURFACERe~ct,~>ContainmentSprayHeatExchanger122100001010%ofAllppqpOI>lpp0!tattachments,CodeCaseH-509ITEMTOTAL:81000010O.pit0.0%100.0%C3.20PIPING-INTEGRALLYWELDEDSURFACEControlRodATTACHMENTSDrive0.0%O.pentppgattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseH-50924000000010!tofAllSURFACEEmergencyCondenserReturn618000.OS008010%ofAllppglpppgattachments>LimitedtothoseCategoryC-FandC-G,CodeCaseN-509SURFACEEmergencyCondenserSupply18440000010%ofAll100.0%100.0%Ipp.pitattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseN-509

DATE:10/26/99REVISION:00NINEHILEPOINTttUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIOttXISUHMARYEBTABLINTEGRALATTACHMENTSFORVESSELS,PIPING,PUMPS,ANDPAGE:39CODEED1TION:E89ASMESECXIITENtjITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSttOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOHMENTSSURFACEMainSteam15440000010%ofAlllppptlpppilpppttattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseN-509SURFACEHainSteamSystem568008000lpttofAll00%100Ott100Ottattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseN-509SURFACEReactorContainmentSpray526549025020010%ofAll629tlpppgattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseN"509SURFACEReactorCoreSpray3312613020110105ofAll5p.nit57.6$lpppttattachments,LimitedtothoseCategoryC-FandC-G,CodeCaseN-509ITEMTOTAL:103110430035039028.8t62.5%100.0ttC3.30PUMPS-INTEGRALLYWELDEDATTACHMENTSN/AC3.40VALVES-INTEGRALLYWELDEDATTACHMENTSCATEGORYTOTAL'03910530035040028.5'461.9't100.0t

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUHMARYLEBTABPRESSURERETAININGBOLTINGGREATERTHAN2INCHESINPAGE:40CODEEDITION:E89ASMESECXIITEMirITEHDESCRIPTIONC4.10PRESSUREVESSELS-BOLTSANDSTUDSEXAMMETHODSYSTEMDESCRIPTIONN/ANO.OFCCHPONENTSltOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSC4.20PIPING-BOLTSANDSTUDSC4.auPUMPS-BOLTSANDSTUDSC4~40VALVES-BOLTSANDSTUDSNxhN/nCATEGORYTOTAL:000000000.0%O.OSO.OS

DATE:10/26/99RFV.'SIOHt00tllHEMILEPOItlTtlVCLEARPIAIITUNIT1ltlSERVICEltlSlECTI:.>I:PI.AII8'>RTHETtl)RDItlTERVALTAB'BPAGE:41CODEEDITION:E89PRESSURERETAININGWELDSZNAUSTENITICSTAINLESSSTEELASMESECKIITEMtlITEMDESCRIPTIOHEXAMMETHODNO.Of'OMPONENTSSYSTEMttOFHO.SCHEDULED/COMPLETEDDESCRIPTIOHCOMPREQ1STPER2NDPER3RDPERCOMMENTSC5.12LONGITUDINALWELDS>3/8VOLUMETRICEmergencyIN.HOMINALWALLCondenserReturnTHICKNESSFORPIPING>NPS454157030502.5tatlpp0%intersectingCirc.Weldsselectedforexamination,CodeCaseH-524VOLUMETRICEmergencySURFACECondenserSupply672240110702.5tatlppp%intersectingCirc.Weldsselectedforexamination,CodeCaseN-524ITEMTOTAL:1213711014012029.7%67.5%100.0%':KCUMFEKEtlTIALVtEL-1/b1N.NOM1HALWALLTHICKNESSFORPIPINGNPS2AND<NPS4*LONGITUDINALWELDS>1/5IH.NOMINALWALLTHICKNESSFORPIPZHG>NPS2AND<NPS4C5.30SOCKETWELDSH/AC5.41CIRCUMFERENTIALPIPEBRANCHCONNECTIONSOFBRANCHPIPING>NPS2N/AC5.42LONGITUDINALPIPEBRANCHCONNECTIONSOFBRANCHPIPING>NPS2N/ACIRCUMFERENTIALPIPEWELDS>3/8IN.NOMINALWALLTHICKNESSFORPIPING>NPS4VOLUMETRICEmergencySURFACECondenserReturn3184020207.5%butnotless5pp%75p%lppp%than28weldsVOLUMETRICFm.rge>>~ySUKf'ACF.('~>denqi.~>upptytu407060/.5%butnotless5%647%lppp%than28weldsITEMTOTAL:722580908032.0%68.0%100.0%CATEGORYTOTAL:1936219023020030.6%67'%100.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYPAGE:42CODEEDITION:E89TABLEB2-PRESSURERETAININGWELDSINCARBONORLOWALLOYSTEELASMENO.OFCOMPONENTSSECXIEXAHSYSTEMfiOFNO.SCHEDULED/COMPLETEDITEM4ITENDESCRIPTIONMETHODDESCRIPTIONCOMPREQ1STPER2NDPER3RDPERCOMMENTSC5.53CIRCUHFERENTIALWELDS>3/8"NOMINALWALLTHICKNESSFORPIPING>NPS4VOLUHETRICControlRodSURFACEDriye5962020207.58butnotless333%666%1000%than28weldsVOLUMETRICHainSteamSURFACE3031010107.5%butnotless33.3%66.6%100.0%than28weldsVOLUMETRICMainSteamSURFACESystem4962020207.5%butnotless33.3%66.6%100.0%than28weldsVOLUMETRICReactorSURFACEr,i,~ainmg.~3422770801207.5%butnotless25.9>>55.5~lpppgthan28weldsvoLUMETRIcReactorSURFACEConiafnmentSprayPump11100000007.5%butnotless0~0%0.0%0.0gthan28weldsVOLUHETRICReactorContainmentSprayPump11200000007.5%butnotlessppgppgppgthan28weldsVOLUMETRICReactorSURFACEContainmentSprayPump121200000007.5%butnotlessppgppgppgthan28weldsVOLUHETRICRe~tn!SURFA'00000007.5%butnotless0pgppgthan28weldsVOLUMETRICReactorCor.SURFACESpray225218070607.5%butnotless38pg714glpppgthan28welds 0

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANfORTHETHIRDINTERVALCLASS2SECTIONXISUYMARYPAGE:43CODEEDITION:E89TABLEBPRESSURERETAININGWELDSZNCARBONORLOWALLOYSTEELASMESECXIITEM5ITEMDESCRIPTIONCS.51EXAMMETHODSYSTEMDESCRIPTIONNO~OfCOMPONENTSIOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMHENTSVOLUMETRICReactorCoreSURFACESprayPump111200000007.5SbutnotlessppSppSppSthan28weldsVOLUMETRICRe~or~aCor~rl'llL'I,'Fai.-r,lyiurnj00000007.5SbutnotlesspOSp.pSppSthan28weldsVOLUHETRICReactorCoreSURFACESpraypump121200000007.5Sbutnotlessp.pSp.pSp.pStharr28weldsVOLUMETRICReactorCoreSURFACESpraypump200000007.5SbutnotlessppSppSpOSthan28weldsITEHTOTAL:7216320020023031.7S63.4S100.OSC5.52LONGITUDINALWELDS>3/8"VOLUMETRICReactorNOHINALWALLTHICKNESSSURFACEContainmentFORPIPING>NPS4Spr*yPumpl1]200000O.OSO.OS002.5tatppSintersectingCirc.welds,CodeCaseN-524VOLVHETirl",Re-~".:ContainmentSprayPump112uv00O.OSO.OSv02.5tatp.pSintersectingCirc.welds,CodeCaseN-524VOLUMETRICReactorContainmentSprayPump121O.OS0.0'SpOSintersectingCirc.welds,CodeCaseN-524200000002StatVOLUMETRICReactorContainment.SprayPump122200000O.OSO.OS002.5tatppSintersectingCirc.welds,CodeCaseN-524

DATE:10/26/99REVISION:00NittEMILEPOINTtfUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIOftXlSUMMARYPAGE:44CODEEDITION:E89TABLEBPRESSURERETAININGWELDSINCARBONORLOWALLOYSTEELASMESECXIITEMttITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOf'O.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVOLUMETRICReactorCoreSURFACESpraypump200000O.pftO.pt002.5tatppftintersectingCirc.welds,CodeCaseN-524VOLUMETRICReactorCoreSURFACESpraypump0.Oft0.0%p,pftintersectingCirc.welds,CodeCaseN-524200000002.5tatVOLUMETRICReact>rC~reSURFACESpraypumplpl00000O.pft0.0%002.5tatppftintersectingCirc.welds,CodeCaseN-524VOLUMETRICReactorCoreSURFACESptaypumk"2000000.040.Pf!002.5tatppftintersectingCirc.welds,CodeCaseN-524ITEMTOTAL:1600000000.0%0.0%0.0%C5.61CIRCUMFERENTIALWELDS>1/5"NOMINALHALLTHICKNESSFORPIPING>NPS2AND<NPS4N/AC5.62LONGITUDINALWELDS>'1/5"tfOMINALWALLTHfCKNL'SSFOR1".f11t(1ttPS'Nb~NPSN/AC5.70SOCKETWELDSNIA'5.81CIRCUMFERENTIALPIPEBRANCHCONNECTIONSOf'RANCHPIPING>NPS2SURf'ACEtfainSteamSystem1610010007.5L,Butnotlessppglpppftlpppftthan28weldsSURFACEReactorContainmentSpkay611000007.5L,Butnotlesslpppftlpppqlpppftthan28weldsSURFACEReactorContainmentSprayPump111200000007.5%,Butnotlessppftppgppgthan28welds

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYPAGE:45CODEEDITION:E89TABLEBPRESSURERETAININGWELDSINCARBONORLOWALLOYSTEELASMESEC/1ITEMIITEMDESCRIPTIONE.'iAMMETHODSYSTEMDESCklP'f'lONNO.OFCOMPONENTSffOFNO.SCHEDULED/COMPLETEDCOMf'EO1STPER2NDPER3RDPERCOMMENTSSURF'ACEReactor00000007.5%,ButnotlessContainmentp.p%p.p%p.p%than28weldsSprayPump112SURFACEReactorContainmentSprayPump121210000107.5%,Butnotlesspp%pp%lppp%than28weldsSURFACEReactorContainmentSprayPump122200000007.5%,Butnotlesspp%pp%pp%than28we)dsSURFACEReactorCoreSprayPump111200000007.5%,Butnotlesspp%pp%pp%than28weldsSURFACEReactorCoreSprayPump11."00000007.5%,Butnotless0.0%p.p%p.p%than28weldsSURFACEReactorCoreSprayPump1"1200000007.5%,Butnotless0.0%0.0%p.p%than28weldsSURFACEReactorCoreSprayPump122200000007.5%,Butnotlesspp%pp%pp%than28weldsITEMTOTAL:38310101033.3%66.6%100.0%C5.82LONGITUDINALPIPEBRANCHCONNECTIONOFBRANCHPIPING)NPS2N/ACATEGORYTOTAL:7756621021024031.8'%3.6%100.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYTABLEBPAGE:46CODEEDITIONtE89PRESSURERETAININGWELDSZNPUMPSANDVALVESASMESECXIITENNITEMDESCRIPTIONEXAMHETHODSYSTEHDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOHMENTSC6.10PUHPCASINGWELDSSURFACEReactor100000000OnlyonepumpContainment0Og0Og0OgamongeachgroupSprayPump111ofpumpSURFACEReactorContainmentSprayPump112100000000Onlyonepump0.0tt0Og0OgamongeachgroupofpumpSURFACERea.torConc~>raietitSprayPump1"1105104000Onlyonepump0011000%100OiamongeachgroupofpumpSURFACEReactorContainmentSprayPump122100000000Onlyonepump0Ott0Og0OttamongeachgroupofpumpSURFACEReactorCoreSprayPump111100000000Onlyonepump0Og0Og0OgamongeachgroupofpumpSURFACF.Ria"t~:~"r"SprayPump11'<<0000000Onlyonepump0Oi0Og0OttamongeachgroupofpumpSURFACEReactorCoreSprayPump121104000040Onlyonepump0Ot,0Ott100OgamongeachgroupofpumpSURFACERect.orCoreSprayPuaip1"2100000000OnlyonepumpO.Ott0.0tt0.0%amongeachgroupofpumpZTEMTOTAL:80910404011.1%55.5%100.0%C6.20VALVECASINGWELDSCATEGORYTOTAL:80910404011.11O.OS100.08.

LITNlAGARAHUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECT(ONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev:0Date:September27,1999TableofContentsTABLEOFCONTENTSAPPENDIXC-CLASS3SUMMARYTABLESC-1RecordofRevisionASMECodeClass3SectionXISummaryTables.ExaminationCategoryD-AC-2C-347-48File:APPENDIXC.WPD

EIYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REVISION"'ATERECORDOFREVISIONAFFECTEDPAGESREASONFORREVISIONI"0September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFiie:APPENDIXC.WPD

YNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ASMECODECLASS3SUMMARYTABLESFile:APPENDIXC.WPD 0

DATE<lp/26/99REVISION:00NlNEMllEP<,<lNTNUCLEARPLANTUNIT'NSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYTABLEBPAGE:g7CODEEDITION:E89INTEGRALATTACHMENTSFORCLASS3VESSELS<PIPING<PUMPS<ASMESECXIITEMllITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSIIOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMFNTSDl.lpPRESSUREVESSELINTEGRALLYWELDEDATTACHMENTSVISUALEmergencyCondenserHeatExchanger111300000O.plO.pll001008ofweldpplllength,CodeCaseN-509,104requiredVISUALEmergencyCondenserHeatExchanger112300000O.OSO.pl<001008ofweldO.pglength,CodeCaseN-509,108requiredV'UAl.E<<<':"g<<'f<"/u~<<,<<I<,(,<<<00V00001004ofweldlength,CodeCaseH-509,104requiredVISUALEmergencyCondenserHeatExchanger12233000.Ol<0030100<iofweldppglpppalength,CodeCaseN-509,10%requiredVISUALReactorBuildingClosedLoopCoolingHeatExchange622000001008ofweldlppplllpppl,lppp<llength,CodeCaseN-509,10%requiredVISUALShutdownCoolingWaterHeatExchanger1122000.0%0020100%ofweldpp<llppplllength,CodeCaseH-509,10%requiredVISUALSl<<<<~iw;<~'.i<<Ipp<,>.0%u.0100100%ofweld0pglength,CodeCaseN-509,10%requiredVISUALShutdownCoolingWaterHeatExchanger132000000.O'L0.Ol<00100%ofweldppl<length,CodeCaseN-509,10%requiredVISUALSpentFuelPool20000000100%ofweldCoo)ingHeatppgpp<lpplllength,CodeCaseExchanger11N-509,10%

DATE:10/26/99REVISIOH:00HINEMILEPOIHTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYPAGE:48CODEEDITION:E89TABIECINTEGRALATTACHMENTSFORCLASS3VESSELS,PIPING,PUMPS,ASMESECXIITEMj>ITEMDESCRIPTIOHEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSDl.10VISUALSpentFuelPoolCcnlingHeatExchanger122000.0%required0020lppttofweldppttlpppglength,CodeCaseN-509,1pttrequiredITEMTOTAL:28920007022.2'2.2S100.0'tD1.20PIPINGINTEGRALLYWELDEDVISUALEmergencyATTACHMENTSServiceWater292000.0%0020lppttofweldpptjlpppglength,10$ofallintegralattachments,CodeCaseN-509VISUALReactorBuildir>g537ClosedLoopCooling002050100%ofweldO.ptt28.5%100.0%length,10%ofallintegralattachments,CodeCaseN-509VISUALReactorC'rajnm>et>rSpray"19151500000100%ofweld100.0%100.0%100.0%length,10%ofallintegralattachments,CodeCaseN-509VISUALSpentFuelPoolCooling158200016040100%ofweldp.pttBppjtlpppglength,lptjofallintegralattachments,CodeCaseN-509ITEMTOTAL:45944150180110s4.0%75.0t>lpp.ptjDl.3uPUMPSINTEGRALLYWELDEDATTACHMENTSNtADl.40VALVESINTEGRALLYWELDEDATTACHMENTSCATEGORYTOTAL:4875317018018032.0tj66.0t100.0'1

YNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TABLEOFCONTENTSAPPENDIXD-CLASS1,2,3COMPONENTSUPPORTSUMMARYTABLESTableofContentsRecordofRevision.ASMECodeClass1,2,3SectionXIComponentSupportSummaryTables..ExaminationCategoryF-AASMECodeClass1SupportsASMECodeClass2SupportsASMECodeClass3SupportsOtherThanPipingSupports.D-1D-2D-349-5849-5151-5252-5353-58File:APPENDIXD.WPD

hlYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999REVISIONRECORDOFREVISIONAFFECTEDPAGES.REASONFORREVISION0September27,1999EntireDocumentUpdatedInserviceInspectionProgramPlanforthe3"TenYearlnserviceInspectionIntervalFile:APPENDIXD.WPD

TNIAGARAUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999ASMECODECLASS1,2,3COMPONENTSUPPORTSUMMARYTABLESFile:APPENDIXD.WPD

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANfORTHETHIRDINTERVALCLASS2SECTIONXISUHMARYTABLECPAGE:49CODEEDITZON:E89ClassIPipingSupportsASHESECXZITEHIITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOHMENTSFl.lp25%ofClass1VISUALControlRodDrive100010Categorizedto50.0i50.0'i100.08identifysuPPorttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALEmergencyCondenserReturn153100020Categorizedto333$333QlpppiidentifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALFeedwaterSystem185102020Categorizedto2ppq60pglpppgidentifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491"1VISUALLiquidPoison7101000Categorizedto50.0%100.0%100.0%identifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALHainSteamSystem16101020Caregorizedto25pi5ppilppptientyupporttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALReactorCleanUp182100010Categorizedto5ppg5ppiIpp.pqidentifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALReactorCoreSpray6202020Categorizedtolpppiidentifysupport

DATE:10/26/99REVISIOH:00N1WEMiLL'VltlTNUCLEARPt&flTUNIT1INSERVICEINSPEC1OtlPLAtlFORTHETHIRDINTERVALCLASS1SECL'IOtlilSUMMARYTABLEDPAGE:50CODEEDITION:E89-Class1PipingSupportsASMESECXIITEMttITEMDESCRIPTIONFl.10EXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTStypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALReactorDrain100010Categorizedto50.0tt50.0$100.0%identifysuPPrttypesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALReactorHeadVent102101000Categorizedtoipppttiden'tifysuppor'ttypesbycomponentfunctionA,B,C,etc,CodeCaseH-491-1VISUALReactorInstrumentation41000.0%0010Cat:egorizedtop.pttlpppgidentifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseH-491-1VISUALReactorRecircuiationDischarge3082025.0'1020Categorizedto01lpppiidentifysupport.typesbycomponentfunctionA,B,C,etc,CodeCaseN-491-1VISUALReactorRecirculationSuction258202040Categorizedto25.ptt5ppgipppitidentifysupporttypesbycomponentfunctionA,B,C,etc,CodeCasetl-491-1VISUALReactorShutdownCooling81000.0%0010Categorizedtop,pglpppt,identifysupporttypesbycomponentfunctionA,B,C,etc,CodeCaseH-491-1

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUtlIT1INSERVICEINSPECTIONPLAtlFORTHETHIRDItlTERVAL'tJd::tSE/IutiXiSUMMARYTABLEDPAGE:51CODEEDITION:E89Class1PipingSupportsASMESECXIITEMttITEMDESCRIPTIONEXAMMETHODSTSTEMDESCRIPTIONNO.OFCOMPONENTSftOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSITEMTOTAL:1904614013019030.4tt58.6tt100.0%F1.2015%ofClass2SupportsVISUALControlRodDrive324300010Categorizedto75~0%75.0tt100.OttidentifysupporttypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1VISUALEmergencyCondenserReturn313001020Categorizedto001333tt1000$identifysupporttypesbycomponentfunctionA,B,C,etc.CodeCaseN"491"1VISUALEmergencyCondenserSupply323300000Categorizedto100.0'1100.0tt100.OtalidentifysuPPorttypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1VISUALMainSteam132200000Categorizedto1000tt100Otal1000ttidentifysupporttypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1VISUALMainS>~amS'/s~em3430<3000Categorizedto1000<1000ttidentifysupporttypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1VISUALReactorContainment178281409050Categorizedto50.0%82.1tt100.0Sidentifysupport

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANfORTHETHIRDINTERVALCLASS3SECTIONXISUMHARYTABLEFPAGE:52CODEEDITION:E89Class2PipingSupportsASHESECXIITEH5ITEHDESCRIPTIONFl.20EXAMMETHODSYSTEHDESCRIPTIONSprayNO.OfCOMPONENTSllOFNO.SCHEDULED/COMPLETEDCOHPREQ1STPER2NDPER3RDPERCOMMENTStypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1VISUALR'.i"',~iCoreSpkey706090Categorizedto318t59Ot100OtidentifYsupporttypesbycomponentfunctionA,B,C,etc.CodeCaseN-491-1ITEMTOTAL:4336529019017044.6t73.8t100.0tF1.3010tofClass3SupportsVISUALEmergencyServiceWater576301020Categorizedto50.0t66.6t100.0tidentifytypesbycomponentsupportfunctionA,B,C,etc.CodeCaseN-491-1VISUALReactorBuildingClosedLoopCoolinp214190040150Categorizedto0Ot21Ot100OtidentifytypesbycomponentsupportfunctionA,B,C,etc.CodeCaseN-491-1VISUALReactorContainmentSpray140151005000Categorizedto66.6t100.0t100.0tiden<<fytypesbYcomponentsupportfunctionA,B,C,etc.CodeCaseN-491-1VISUALSpentFuelPool200000Cooling0.0't0.Ot00Categorizedto0OtidentifytypesbycomponentsupportfunctionA,B,C,etc.CodeCaseN-491-1

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS3SECTIOttXISUMMARYTABLEFPAGE:53CODEEDITION:E89-Class3PipingSupportsASMESECXIITEMttITEMDESCRIPTIONFl.30EXAMMETHODSYSTEMDESCRIPTIONHO.OFCOMPONENTSOFHO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSCategorizedtoidentifytypesbycomponentsupportfunctionA,B,C,etc.CodeCaseH-491-1VISUALSpentFuelPoolcoilingSystem51000.0%0010Chtegorizedto00%1000%identifytypesbycomponentsupportfunctionA,B,C,etc.CodeCaseH-491-1ITEMTOTAL:503511401702002t.4%60.t%100.0%Fl.40100%ofthesupports,Formultiplecomponents,onlyoneofmultiplecomponentsrequiredVISUALEmergencyCondenserHeatExchanger11110000000CodeCaseH-491-10.0%0.0%0.0%VISUALEmergencyCondenserHeatExchanger11210000000CodeCaseN-491-10.0%"0.0%0.0%VISUALEmergencyCondensrt!.AL10000000CodeCaseH49110.0%0.0%0.0'%lSUALEmergencyCondenserHeatExchanger12211v00010CodeCaseH-491-10.0%0.0%100.0%VISUALEmergencyServiceWaterPumpll11000010CodeCasett-491-10.0%0.0%100.0%VISUALEmergencyServiceWaterPump121~0000000CodeCasett-491-10.0%0.0%0.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS3SECTIONyISUMHARYTABLEFPAGE:54CODEEDITION:E89-SupportsOtherThanPipingSupportsASMESECXIITEMjjITEMDESCRIPTIONEXAMHETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSjjOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVISUALHainSteam11000010CodeCaseN-491-1O.OL0.0jj100.0'tVISUALReact:orBuildingClosedLoopCoolingHeatExchange31100000CodeCaseN-491-1.100.05100.0'00.0tjVISUALReactorBuilding11000010CodeCaseN-491-1ClosedLoop0'jjO.OS100.0jjCoolingHUTankVISUA!,RPqtt.+IR<j1djncjnn0010CodeCaseN-491-10.0e0.0%100.0%VISUALReactorContainmentSprayHeatExchanger11110000000CodeCaseN-491-10.0%0.080.0'jVISUALReactorContainmentSprayHeatExchanger1120000000CodeCaseN-491-10.0jj0.0%0.0'5VISUALReactorContainmentSprayHeatExchanger12110000000CodeCaseN-491-1O.OS0.0'.0%VISUALReactorContdinlfLenl11100000CodeCaseN-491-1100.0'4100.0%100.04VISUALReact.orContainmentSprayPump11110000000CodeCaseN-491-10.0jj0.0%0.0%

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIOHXISUMHARYTABLEEPAGE:55CODEEDITIOHtE89SupportsOtherThanPipingSupportsASHESECXIITEMhITEMDESCRIPT!OHFl.4vEXAHHET!ivvSYSTEMDESCRIPTIOlrNO.OFCOMPONENTSfiOFHO.SCHEDULED/COMPLETEDCOMPREQISTPER2NDPER3RDPERCOHMENTSVISUALReactorContainmentSprayPump112I0000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorContainmentSprayPump121I1100000CodeCaseN-491-1100.0%100.0%100.0%VISUALReactorContainmentSprayPump12210000000CodeCaseH-491-10.0%0.0%0.0%VISUALReactorContainmentSP.<<'/kawWetert'irrfeII00I000CodeCaseH-491-10.0%100.0%100.0%VISUALkeact.ul'ontainrrient,SprayRawWaterPump112!u000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorContainmentSprayRawWaterPump12110000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorContainmentSprayRawWaterPump122I0000000CodeCaseH-491-10.0'%.0%0.0%VISUALReactorCoreSprayPumpI!I10000000CodeCaseH-491-1D.0%O.0'%.0%VISUALke9".torCttt'prayPurr'1"!r'ru00000CodeCaseH-491-10.0%0.0%0.0%

DATE:10/26/99REVISION:00NINEHILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS2SECTIONXISUMMARYTABLEEPAGE:56CODEEDITION:E89-SupportsOtherThanPipingSupportsASHESECXIITEH8ITEMDESCRIPTIONFl.40EXAMMETHODSYSTEHDESCRIPTIONNO.OF'OMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMHENTSVISUALReactorCoreSprayPump12110000000CodeCaseN-491-10.0%0.0%0.0'%ISUALReactorCoreSprayPump12210000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorCoreSprayToppingPump11111100000CodeCaseN-491-1100.0%100.0%100.0%VISUALReactorCoreSprayToppingPump11210000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorCoreSprayToppingPump12110000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorCoreSpr~yTrpplng10000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorRecirculationPump1171001000CodeCaseN-491-10.0%100.0'%00.0%VISUALReactorRecirculationPump1270000000CodeCaseN-491-10.0%0.0'%.0%

DATE:!u/26/99REVISIO!f:00WINEMILEPOINTNUCLEARPLANTUtkIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS1SECTIONVISUMHARYTABLEDPAGE:57CODEEDITION:E89SupportsOtherThanPipingSupportsASMESEC/IITENEITEMDESCRIPTIONE'1.40EXAMMETHODSYSTEMDESCRIPTIONReactorRecirculationPump13NO.OFCCHPONENTSfkOFWO.SCHEDULED/COHPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVISUALReactorRecirculationPump1470000000CodeCaseN-491-10.0%0.0%0.0%VISUALReactorRecirculationk'Umf71001000CodeCaseN49110.0%100.0%100.0%VISUALRe<<t.ocVesselSupports99202050CodeCaseN-491-122.2%44.4%100.0%VISUALShutdownCnnling11000010CodeCaseN-491-1WaterHeat0.0%0.0%100.0%Exchanger11VISUALShutdownCooling10000000CodeCaseN-491-1WaterHeat0.0%0.0%0.0%Exchanger12VISUALSkiutdownCooling10000000CodeCaseW-491-1WaterHear0.0%0.0%0.0%VISUALSpentFuelPool11001000CodeCaseW-491-1CoolingE'liter0.0%100.0%100.0%llVISUALSpentFuelPool10000000CodeCaseN-491-1CoolingE'ilter0.0%0.0%0.0%l~

DATE:10/26/99REVISION:00NINEMILEPOINTNUCLEARPLANTUNIT1INSERVICEINSPECTIONPLANFORTHETHIRDINTERVALCLASS3SECTIONXISUMMARYTABLEFPAGE:58CODEEDITION:E89SupportsOtherThanPipingSupportsASMESFCXIITEMi>>>ITEMDESCRIPTIONEXAMMETHODSYSTEMDESCRIPTIONNO.OFCOMPONENTSOFNO.SCHEDULED/COMPLETEDCOMPREQ1STPER2NDPER3RDPERCOMMENTSVI8>.'A>:>i.:,>F>>nlPool>)1>:Heatx'ha>>g"r110000000CodeCaseN-491-10.0%0.0%0.0%VISUAlSpentFuelPoolCoolingHeatExchanger1211001000CodeCaseN-491-10.0%100.0%100.05VISUALSpentFuelPool11000010CodeCaseN-491-1CoolingPump110.0%O.OS100.0%VISUALSpentFuelPool10000000CodeCaseN-491-1CoolingPump120.0%0.0%0.0%V:.UAL1000CodeCaseN-491-1]>>'0.0>>100.0$ITEMTOTAL:8926608012023.0%53.88100.0%CATEGORYTOTAL:121518863057068033.5063.8%100.0%

hlVNlAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContentsRecordofRevisionTABLEOFCONTENTSAPPENDIXE-CODEBOUNDARYDIAGRAMSE-2ASMECodeBoundaryClassificationDiagramListing.E-3Fiie:APPENDIXE.WPD

NUMOHAWKYNAGARANineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999~.:~AX~~"','9"'~""-.~,REC@AD.'OF;RBVf8ION"-.~+,,;mme%-.Sinai~;~.:;-,'='-:.".."."",-'";;>',ZPR~~~4~~.";REVISlON40PAGES+%~@+>September27,1999EntireDocumentTREASONFOR;REVISION::;",,'"-...'4'APcUpdatedInserviceInspectionProgramPlanforthe3"TenYearInserviceInspectionIntervalFile:APPENDIXE.WPD

hlVNIAGARAaUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999CODEBOUNDARYCLASSIFICATIONBOUNDARYDIAGRAMSTheNMP1CodeBoundaryClassificationDiagramsidentifyingQualityGroupA,BandC(ASMECodeClass1,2and3)systemsaredescribedbelow.CODEBOUNDARYDIAGRAMLISTINGBoundaryDiagramNumberF-63002-CF-63003-CF-63005-CF-63006-CF-63007-CF-63008-CF-63009-CF-63011-CF-63012-CF-63013-CF-63014-CF-63015-CF-63016-CF-63017-CF-63018-CF-63019-CF-63020-CF-63021-CF-63022-CF-63026-CF-63027-CF-63035-CF-63036-CSystemTitleMainSteamandHPTurbineCondensateFlowHighPressureFWFlowDrywellandTorusIsolationValvesReactorCoreSpraySpentFuelStoragePoolFilter&CoolingReactorCleanupSystemInstrumentAirReactorContainmentSprayReactorBuildingHeatandCoolingDrywell&TorusInertGas&CoolingReactorvesselInstrumentationControlRodDriveEmergencyCoolingSystemReactorShutdownCoolingReactorLiquidPoisonSystemReactorRecirculationLoopsTurbineBuildingHeating&CoolingServiceWater,ClosedLoopCoolingDieselGeneratorAir,Water,Oil&FuelServiceWaterResinTransferRegenerationSealingWaterFile:APPENDIXE.WPD

ElVNIAGARAH@MOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999CODEBOUNDARYDIAGRAMLISTINGBoundaryDiagramNumberF-63041-CF-63045-CF-63046-CF-63047-CF-63048-CSystemTitleSamplingWasteDisposalAirConditioningHeating,Ventilating8AirConditioningCondensateTransferFile:APPENDIXE.WPD

YNIAGARAUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999TableofContentsTABLEOFCONTENTSAPPENDIXF-RELIEFREQUESTSF-1RecordofRevisionRequestsforReliefSummary.ISI-1F-2F-31-1of1-8ISI-2ISI-3ISI-4ISI-5ISI-6ISI-7ISI-8ISI-9ISI-10ISI-11ISI-122-1of2-83-1of3-74-1of4-45-1of5-56-1of6-37-1of7-48-1of8-69-1of9-310-1of10-311-1of11-112-1of12-3File:APPENDIXF.WPD

ElYNIAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999',".'""..I<""-".RECORD'OFIREVISION;..":,";.:.'i';"'",~".""':-""""'~"';-'".'",."'".":."'".",,",;"".'REVISION>>0,'<'"','DATE'"September27,1999AFFECTED.",;.:".".:i:,";PAGESl..","--"':.".':.-"'EntireDocument'-REASON'FORREVISION;,'.;UpdatedInserviceInspectionProgramPlanforthe3"TenYearInseiviceInspectionIntervalFile:APPENDIXF.WPD

VNlAGARAUMOHAWKNineMllePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999CLASS1,2AND3RELIEFREQUESTSUMMARYRelief'Req.',No.ISI-1ISI-2ISI-3ISI-4System'.or'ompo'nent;.,:,ReactorPressureVesselReactorPressureVesselReactorPressureVesselReactorPressureVesselExam.Cat;g'.,-,-,"8-A8-A8-D8-A(Exam,',,'item:",;No;,-':,81.1181.1281.2181.2281.3081.4083.9083.10081.3081.12Su'm'mary.'of,R'equest""',forReliefReliefisrequestedforpermanentrelieffromexaminingRPVCirc.WeldsReliefisrequestedfromtheperforming100%ofweldlengthRequestRelieffromperforming100%ofCRVReliefisrequestedfromIWB-2420(b)reexaminationrequirements..ProposedAlternatives-t."<NMPCproposestoperformexaminationasdefinedintheReliefRequestPerformexamstotheextentpracticalPerformexamstotheextentpracticalNMPCproposestoutilizeASMECodeCaseN-526,"AlternativeRequirementsforSuccessiveInspectionsofClass1and2Vessels"ReliefRequestStatus,GrantedTACMA4383ISI-5ISI-6ISI-7ReactorPressurevesselsReactorPressurevesselReactorContainmentSpray&ReactorCoreSprayPumps8-K8-0C-G810.10814.10C6.10Reliefisrequestedfromperforming100%ofweldlengthReliefisrequestedfromperforming100%ofCRAReliefisrequestedfromperformingexaminationof100%weldsononepumpamonggroupofpumpsNMPCproposestoperformadditionalexamperReliefNMPCproposestoperformadditionalexamperReliefRequestPerformexaminationstotheextentpracticalfromtheoutsidesurface,andfromtheinsidewhendisassembledFile:APPENDIXF.WPD

HYNlAGARAHUMOHAWKNineMilePointNuclearPowerStationUnit1THIRDINSERVICEINSPECTIONINTERVALINSERVICEINSPECTIONPROGRAMPLANNMP1-ISI-003Rev.0Date:September27,1999CLASS1,2AND3RELIEFREQUESTSUMMARYReliefReq.'o.*":i,"'::.':;:".:..':-',SysteIncia,Comp'onent,:,;;,Exa'm'~'at.,*.".'.';.Sx'a'm~",".-'SummarjjofRequest':;.;:-'forRelief,.',,';:;~'-;Proposed'Alternatives:Retief.:...':-.',",Reque'st.;StatusISI-8ISISummaryReportIWA-6000N/AN/AReliefisrequestedfromArticleIWA-6000NMPCproposestoutilizeASMECodeCaseN-532,"AlternativeRequirementstoRepairandreplacementDocumentationRequirementsandInserviceSummaryReportPreparationandSubmissionasRequiredbyIWA-4000andIWA-6000"Sl-9ASMECodeClass1,2N/AN/Aand3SnubbersReliefisrequestedfromSection2.3.2.2and2.3.2.3ofOM-1988,Part4andArticleIWFNMPCproposestoutilizeUSNRCGenericLetter90-09forintervalsandsamplingrates,performexamsinaccordancewithPlantTechSpecsISI-10ArticleIWA-4000N/AN/AReliefisrequestedfromtherequirementsofArticleIWA-4000,IWA-4400NMPCproposestoutilizeASMECodeCaseN-573,"TransferofProcedureQualificationRecordsbetweenOwners"ISI-11ISI-12ReactorVesselClosureB-G-1B6.10HeadNutsQualityGroupA,ASMEN/AN/ACodeClass1AugmentedExaminationsReliefisrequestedfromperforming100%surfaceexaminationof64RVCHNutsReliefisrequestedfromperformingfullvolumetricandsurfaceexaminationof21nonconformingservicesensitivepipingweldsNMPCproposestoutilizetheVisualVT-1examinationcriteriaofthe1989AddendaNMPCproposestoutilizeVolandSurfaceexamstotheextentpracticalandVT-2eachoutageforevidenceofleakageFile:APPENDIXF.WPD

NINEMILEPOINTUNIT)THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1ONENTIDE0ReactorPressureVesselQualityGroupA,ASMECodeClass1System:Class:ComponentDescription:ReactorPressureVesselShellWeldsETIONEASMESectionXI,TableIWB-2500-1,ExaminationCategoryB-A,"PressureRetainingWeldsinReactorVessel,ExaminationItemNumberB1.10,"ShellWelds",CircumferentialNefdsRVWD-100RVWD-101RVWD-137RVWD-138RVWD-130RVWD-132RVWD-134RVWD-139AxialVfetds";'-'..:-.."..RVWD-131RVWD-133RVWD-135RVWD-140RVWD-141RVWD-143RVWD-142RVWD-14410CFR50.55a(g)(6)(ii)(A)(2)statesthatalllicenseesshallaugmenttheirreactorvesselinserviceinspectionprogrambyimplementingtheexaminationrequirementsforReactorPressureVesselshellweldsspecifiedinCodeItemNo.B1.10ofExaminationCategoryB-A,PressureRetainingWeldsinReactorVessel,TableIWB-2500-1ofSubsectionIWBofthe1989EditionofSectionXI,DivisionI,oftheASMEBoilerandPrcssureVesselCode,andsubjecttotheconditionsspecifiedin10CFR50.55a(g)(6)(ii)(A)(3)and(4).Asstatedin10CFR50.55a,forthcpurposesofthisaugmentedexamination,essentially100percentasusedinTableIWB-2500-1meansmorethan90percentoftherequiredexaminationvolumeforeachweld.Additionally,IOCFR50.55a(g)(6)(ii)(A)(5)requireslicenseesthatareunabletocompletelysatisfytheaugmentedReactorVesselshellweldexaminationrequirementtosubmitinformationtotheUnitedStatesNuclearRegulatoryCommission(USNRC)tosupportthcdetermination,andproposeanalternativetotheextentnecessaryastoprovideanacceptablelevelofqualityandsafety.RELIEFEUEEDPursuanttoUSNRCGenericLetter98-05,"BoilingWaterLicenseesUseoftheBWRVIP-05ReporttoRequestRelieffromAugmentedExaminationRequirementsonReactorPressureVesselCircumferentialShellWelds."NMPCrequestspermanentrelieffromtheinserviceinspectionrequirementsof10CFR50.55a(g)forvolumetricexaminationofcircumferentialreactorpressurevessel(RPV)welds(ASMESectionXI,TableIWB-2500-1,ExaminationCategoryB-A,ExaminationItemNumberB1.11.D.ELIMINATIONOFREACTORPRESSUREVESSELCIRCUMFERENTIALWELDSFROMINSPECTIONOnNovember10,1998,theUSNRCissuedGenericLetter98-05,"BoilingWaterReactorLicenseesUseOfTheBWRVIP-05ReportToRequestReliefFromAugmentedExaminationRequirementsonReactor.PressureVesselCircumferentialShellWelds"TheLetterstatedthatBWRlicenseesmayseekFile:RRISI1.WPDISI1-1ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-0permanentrelieffromperformingexaminationsoftheRPVcircumferentialshellweldsforthedurationoftheoriginaloperatinglicenseThisdeterminationwassupportedbyUSNRCstaffsSafetyEvaluationReporttotheBWRVIP,datedJuly28,.'1998whichwouldrequire,onaplantspecificbasis,licenseestodemonstratethat:(1)attheendofaunitslicensetheRPVcircumferentialweldswillcontinuetosatisfythelimitingconditionalfailureprobability,and(2)licenseeshaveimplementedoperatortrainingandestablishedproceduresthatlimitthefrequencyofbeyonddesignbasislowtemperatureover-pressureevents(LTOP)tothelimitsspecifiedinusNRCSafetyEvaluationReport.Theplantspecificevaluationagainstbothcriteriaisprovidedbelow.Demonstrateattheendoflicense,thecircumferentialweldswillsatisfythelimitingconditionalfailureprobabilityforcircumferentialweldslntheUSNRCstaffsJuly28,1998,safetyevaluationtotheBWRVIP-05report.Table1illustratesthatNineMilePointUnit1(NMP1)hasconservatismincomparisontotheUSNRCFinalEvaluationofBWRVIP-05LimitingPlantSpecificAnalysis.Thechemistryfactor,adjustmentofthereferencetemperature(cRT,>>),andmeanRT>>,arecalculatedconsistentwiththeguidelinesofUSNRCRegulatoryGuide1.99,Rev.2.ThedatapresentedforNMP1intheBWRVIPresponsetotheUSNRCRequestForAdditionalInformation(RAI)onBWRVIP-05isalsoshowninTable1.ThefluencevalueonTable1boundsthehighestfluencebeltlinecircumferentialweld.ThemaximumCu%andNi%variabilityfromthemostcurrentdataavailableisalsobounded.PARAMETERDESCRIPTIONTABLE1NMP1COMPARATIVEPARAMETERSAT32EFPY(BOUNDINGCIRCUMFERENTIAL1ljbj'ELD)USNRCLIMITINGPLANTSPECIFICANALYSISPARAMETERSAT32EFPYSETABLE2.$4Fluence,n/cm'nitialRT'FChemistrFactorCU7%Ni%ART'FMeanRT'F2.21x10ts-501120.22*0.20*66.516.5SE"VIP"2Px1018151.70.130.7186.486.4SEeCEOGe2.Px10is172.20.1830.70498.198.1Notes:SE=USNRCSafetyEvaluation,entitled,'FinalSafetyEvaluationoftheBWRVesselandInternalsProjectBWRVIP-05Report(TACNO.M93925),"datedJuly28,1998TheCU%andNi%boundsthemaximumGL92-01NMP1weldchemistryvariabilityasdocumentedinNMPC'sSeptember4,1998RAIresponsetoTACNo.MA1200.Asshownabove,theimpactofirradiationresultsinlowerplant-specificmeanRT>>fortheNMP1circumferentialweldmaterialascomparedtothatforanyoftheStaff'splant-specificanalyseswhichwereperformedfortheCEfabricatedRPV'swiththehighestadjustedreferencetemperatures.ComparisonoftheNMP1specificdataandthedatausedintheUSNRCFinalSafetyEvaluationindicatesthedifferenceisthecombinedeffectsoftheNi%andCU%ontheChemistryFactor,whichisbyitselfboundedbytheUSNRCIndependentAssessment,andtheinitialRTQ>>Therefore,thelimitingplant-specificconditionalprobabilityoffailureP(FIE),determinedbytheStaff,boundstheNMP1casethroughtheprojectedendoflicense.ThustheBWRVIPspecificresultsrelativetoNMP1aspresentedinBWRVIP-05andsubsequentRAIresponsesareconsistentwiththoseintheUSNRCIndependentAssessment.BothanalysesconcludethatFile:RRISI1.WPDISI1-2ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1thefailureprobabilityassociatedwiththecircumferentialweldsisextremelysmall,andthatitisordersofmagnitudelessthanthatforaxialwelds.Therefore,theNMP1circumferentialweldsatisfies,attheendoflicense,thelimitingconditionalfailureprobabilityforcircumferentialweldsintheUSNRCStaff'sJuly28,1998,SafetyEvaluation.Demonstratethatlicenseeshaveimplementedoperatortrainingandestablishedproceduresthatlimitthefrequencyofcoldover-pressureeventstotheamountspecifiedinNRCSafetyEvaluationReporttotheBWRVIP,datedJuly2S,199BTheUSNRCstaffindicatedthatthepotentialfor,andconsequencesof,non-designbasiseventsnotdiscussedintheBWRVIP-05reportshouldbeaddressed.Inparticular,theUSNRCstatedthatnon-design,lowtemperatureover-pressuretransients(LTOP)shouldbeconsidered.TheUSNRCfurtherwentontodescribeseveraltypesofeventsthatcouldbeprecursorstoanLTOP.TheBWRVIPprovidedaresponsetothisissueconcludingthatCondensateandControlRodDrive(CRD)pumpscouldcausesuchaconditionleadingtoanLTOPevent.ThiswassummarizedintheUSNRCSafetyEvaluationofBWRVIP-05.NMPChasinplaceprocedureswhichmonitorandcontrolreactorpressure,temperature,andwaterinventoryduringallaspectsofcoldshutdownminimizingthelikelihoodofanRPVLTOPevent.Additionally,theseproceduresarereinforcedthroughNMPC'sreactoroperatortrainingprogram.TheRPVLeakageandHydrostaticpressuretestproceduresusedatNMP1,havesufficientproceduralguidancetopreventLTOP.Theleakagetestisperformedattheconclusionofeachrefuelingoutage,whilethehydrostatictestisperformedonceeverytenyears.Thesepressuretestsareinfrequently-performed,complextasks,andthetestproceduresarecontrolledasSpecialPlantEvolutions.Assuch,arequirementisincludedintheproceduresforanextensivepre-jobbriefingtobeconductedwithallessentialpersonnelincludingOperationsmanagement.Thebriefingdetailstheanticipatedtestingevolutionwithspecialemphasisonconservativedecisionmaking,plantsafetyawareness,lessonslearnedfromsimilarin-houseorindustryoperatingexperiences,theimportanceofopencommunicationsandfinallytheprocessinwhichthetestwouldbeabortedifplantsystemsrespondedinanadversemanner.VesselpressureandtemperaturearerequiredtobemonitoredthroughouttheteststoensurecompliancewiththeplantTechnicalSpecificationpressure-temperaturecuwe.Also,theproceduresrequirethedesignationofa"PrincipalTestEngineer"forthedurationofthetestwhoisasinglepointofaccountability,responsibleforthecoordinationoftestingfrominitiationtoclosure,andmaintainingoperationsandplantmanagementcognizantoftheteststatus.Withregardtoinadvertent','ysteminjectionresultinginanLTOPcondition,NMP1highpressuremake-upsystem,(I.E.,THEHighPressureCoolantInjection(HPCI))aswellasthenormalFeedwatersystemareinterconnected.TheportionofthesystemforHPCIoperationiscomprisedoftwo(2)motordrivencondensatepumps,feedwaterboosterandfeedwaterpumps.HPCIisamodeofoperationoftheCondensateandFeedwatersystemsratherthananindependent,standalonesystem.Assuch,theHPCIsystemcontainsonlyILCcomponentsasitsowndedicatedequipment.HPCIinitiationispromptedbytheReactorProtectionSystemunderthefollowingconditions:(1)aturbinetrip,or(2)lowreactorwaterlevel.Duringshutdownoftheunit,theassociatedboosterandfeedwaterpumpsinthesystemaresecuredinaccordancewithoperatingprocedures.Equipmentmalfunctionorinappropriateoperationalactionwouldbenecessarytocauseinadvertentsystemoperation.Duringnormalcoldshutdownconditions,withtheRPVheadinstalled,RPVlevelandpressurearecontrolledwiththeCRDSystem,CondensateFeedwaterSystem,andReactorWaterCleanup(RWCU)systemsusinga"feedandbleed"process.TheRPVisnottakensolidduringthesetimes,andplantproceduresrequireopeningoftheheadventvalvesafterthereactorhasbeendepressurizedtoapproximately15psig.TheLiquidPoisonSystemisanotherhighpressurewatersourcetotheRPV,however,therearenomeansofautomaticsystemactivation.Systeminjectionrequiresanoperatortomanuallyrepositionakey-lockedcontrolswitchtostartthesystemfromtheControlRoom.Thesystemmayalsobeoperatedfromaremotelocalteststation..TheonlyinjectionpathtotheRPVisthroughtwoexplosiveactuatedinjectionvalvesthatFile:RRISI1.WPDISI1-3ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1areinterlockedwiththekey-lockedswitchintheControlRoom.Localtestingofthepumpsusesdemineralizedwaterfromatesttankandisaclosedtestloop.Theinjectionrateforeachpumpisapproximately30gpm,whichwouldgivetheoperatorsufficienttimetocontrolreactorpressure.Proceduralcontrolsareinplacetorespondtoanunexplainedriseinreactorpressurewhichcouldresultfromaspuriousactivationofaninjectionsystem.Actionsspecifiedincludedeterminationandisolationofthepressuresource,verificationofreactorheadventsand/orMSIVsopenand,asnecessary,relievingreactorpressureusingavailableplantequipment(e.g.,electromagneticreliefvalves,reactorwatercleanupandreactorbottomdrain).Duringnormalcoldshutdownconditions,reactorwaterlevel,temperaturearemaintainedwithinestablishedrangesinaccordancewithoperatingprocedures.TheOperationsmanualgoverningControlRoomactivitiesrequiresthattheControlRoomoperatorsfrequentlymonitorforindicationsandalarmstodetectproblemsandabnormalitiesasearlyaspossible.AnOperationsprocedurealsorequiresthatthecontrolroomsupervisorbenotifiedimmediatelyofanychangeorabnormalityinplantindicationsandcontrols.Furthermore,reactorwaterlevelandtemperatureoperatingbandsandchangestheretoareestablishedunderthedirectionoftheStationShiftSupervisor.Therefore,anydeviationsinreactor-waterlevelortemperaturefromaspecifiedbandwillbeidentifiedandcorrected.Finally,plantconditionsandon-goingactivitiesarediscussedduringeachshiftturnover.Thisensuresthaton-comingoperatorsarecognizantofactivitiesthatcouldadverselyaffectreactorlevel,pressure,ortemperature.PlantspecificprocedureshavebeendevelopedtoprovideoperatorguidanceregardingcompliancewiththeplantTechnicalSpecificationsandRPVpressure-temperaturecurvelimits.Additionally,operatorsreceivetrainingonRPVbrittlefractureandtherelationofthesepressure-temperaturecurvelimits.Duringplantoutages,NMP1workcontrolprocessesensurethattheoutagescheduleandchangestotheschedulereceiveathoroughshutdownriskassessmentreviewtoensuredefense-in-depthismaintained.WorkiscoordinatedthroughtheWorkControlCenterwhichprovidesanadditionallevelofOperationsoversight.IntheControlRoom,theStationShiftSupervisorisrequired,byprocedure,tomaintaincognizanceofanyactivitythatcouldpotentiallyaffectreactorsafetyduringrefuelingoutages.Expectedplantresponsesandcontingencyactionstoaddressunexpectedconditions,thatmaybeencountered,arerequiredtobeevaluatedasstatedintheadministrativecontrolsforriskmanagementandmanagementofoutages.Asdiscussedabove,NMPChasimplementedproceduralcontrolsandtrainingtominimizetheprobalityofanLTOPevent.Accordingly,theaboveinformationandthesupportingtechnicaldocumentationcontainedintheBWRVIP-05reportandUSNRCSafetyEvaluationprovideabasisforexcludingRPVcircumferentialweldsfromtheaugmentedexaminationrequirementsof10CFR50.55a(g)andASMESectionXI.2.WELDACCESSIBILITYNMP1,aBWR/2,hasanRPVthatwasdesignedandfabricatedtotherulesofASMESectionsIandVill,includingNuclearCodeCase1270Nand1273M.Additionally,GeneralElectric'sSpecificationfordesignandfabricationincludedadditionalrequirementsformaterialsandinspectionthatweresimilartoASMESectionIII.Earlyvintageplantsofthistypeweredesigned,fabricatedanderectedpriortotheexaminationandinspectionrequirementsofASMESectionXI.Specificultrasonic(UT)examinationcriteriawasnotrequiredbyASMEI,III,orVillforpreserviceinspectionofthevesselandnotfactoredintotheplantdesign,henceexternalaccesstotheRPVaxialshellweldsisconstrainedduetoinadequateclearancesbetweenthebioshieldwallandvesselinsulation.TheNMP1examinationplanrequiresexaminationof100%ofallaccessibleregionsoftheRPVaxialwelds.Theabilitytoinspect100%oftheaxialweldswillbelimited,insomecases,duetophysicalconstraintsoftheRPVinternalvesseldesignandarrangementofinternalcomponents.AninternalvesselaccessibilitystudyoftheRPVwasperformedbyGeneralElectrictodeterminetheinspectabilityoftheRPVaxialshellweldsandtoobtainclearancemeasurementsfortheGERIS-2000.SeveralinternalvesselcomponentswillFile:RRISI1.WPDISI1-4ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1limita100%IDUTexaminationincludinginterferencefromtheFeedwaterSparger,SpecimenBrackets,VibrationBrackets,theShroudSupportBafflePlate,andShroudRepairTieRodAssembly.Evenwiththeselimitations,theoverallprojectedpercentageofeffectiveweldexaminationcoverageinthebeltlineregionisapproximately92%.Tables2and3provideanillustrationoftheanticipatedexaminationcoverageoftheaxialwelds.IncludedinTable3isacolumnidentifyingthespecificlimitationprecludingessentially100%oftheaxialshellwelds.Adrawingalsoprovidesthelocationofweldsinrelationtothereactorpressurevessel.NMPCconcludedthatpermanentdeferraloftheexaminationoftheRPVcircumferentialshellweldsforthelifeoftheoperatinglicenseandthereducedexaminationcoverageoftheaxialweldsisjustifiedandpresentsanacceptablelevelofqualityandsafetytosatisfytherequirementsof10CFR50.55a(a)(3)(i),10CFR50.55a(a)(3)(ii)and10CFR50.55a(g)(6)(ii)(A)(5).TheproposedexaminationsareanalternativetotheaugmentedexaminationsrequiredforRPVshellweldsspecifiedin10CFR50.55a(g)(6)(ii)(A)(2),andanalternativetotheinserviceinspectionrequirementsoftheASMEBoilerandPressureVesselCode,SectionXI,1989Edition(TableIWB-2500-1,ExaminationCategoryB-A,ItemNo.B1.10).TheproposedalternativeforexaminationoftheRPVshellweldsincludesperforminganexamination,fromtheinternalIDsurface,ofonlytheRPVaxialshellwelds(ItemNo.B1.12)andapproximately2-3percentoftheintersectingcircumferentialRPVshellweld(ItemNo.B1.11)tothemaximumextentpossible.TheexaminationoftheremainingaccessibleportionsoftheRPVcircumferentialshellweldswillbepermanentlydeferredforthelifeoftheoriginalunitlicense.NMPCalsoproposes,aspartofthisrequestforrelief,toperformanautomatedinspectionoftheRPVaxialshellweldsusingpersonnelandproceduresqualifiedtothePerformanceDemonstrationInitiative,(PDI).TheexaminationswillbeperformedusingtheGeneralElectricRemoteInspectionSystem(GERIS-2000).TheGERIS-2000systemandproceduresweredemonstratedandqualifiedtothesatisfactionofPDIandinaccordancewithASMESectionXI,1992Editionwiththe1993Addenda,AppendixVill.ThealternativeprogramidentifiedinAttachment1providesassuranceofstructuralintegrityand,therefore,anacceptablelevelofqualityandsafetyisassured.F.IMPLEMENTATIONSCHEDULEPursuantto10CFR50.55a(a)(3)(i)therequestforreliefwasauthorizedandiseffectivefromthedateoftheUSNRCSafetyEvaluation(4/7/99)untiltheexpirationoftheoperatinglicense(8/22/09),underTacnumberMA4383,datedApril7,1999File:RRISI1.WPDISI1-5ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1TABLE:2.':,".',":;',;;:,~r~'.'",,:,:...:."PROJECTED,EXAMINATlON:COVERAGEOF,RPV.BELTt;INEREGION'AXIAL'WEI.'DS:,;-":;;:,',:;;,:;','WeldNumberID,'VWD-139RVWD-140RVWD-141RVWD-142RVWD-143RVWD-144TOTAL)Weld'Lengthfn'Beftllrie',.",Reglon:,",--:,".'"'"'"""'ln)';;;;;,;;,.'-'128128128404040504ProJectedID'-.ExamfnatlonLength,lnBeltllneRegion(fn)12812891404040467/o,OfWeldLengthIn"BeltllnetobeEx)amfned100%100o/71'/100%100o/100%926o/oTABLE,3,'ROJECTEDEXAWIINATION;COVERAGEOFALLREACTOR;VESSELAXIALWEL'DS.:WeldNumberID.,2RVWD-130RVWD-13'fRVWD-132RVWD-133RVWD-134RVWD-135RVWD-139RVWD-140RVWD-141RVWD-142RVWD-143RVWD-144TOTAL','TotefWeld::',"-""';.",;L'ength:,'-,'"::","'(in)'3213213213313313313213213213313381*1538':;,V>Pr'oJected,lD":';,';;ExamlnatlonTotal;-;:::.'::.,:.';"Length:;";:;.':,-;:(In)13213213276768013213291101101451230';,";;loOfTotalWeld"""<~Lengthto.be',""""':!=',Examined100%100'/100o/57%60%10010068%76%76%63%799%Ca'us'e.'of,L'imitation".'>-",:.-,.'.(See'Notes)F:.FWSFWS,VB,SBFWSSRTRASSBPSSBPSSBPNOTES:FWS-FeedwaterSparger,VB-VibrationBracket,SB-SpecimenBracket,SRTRA-ShroudRepairTieRodAssembly,SSBP-ShroudSupportBafflePlateWeldRVWD-144isrcduccdduetotheintersectionwithaRecirculationNozzleFile:RRISI1.WPDISI1-6ofISI1-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-1ATTACHMENT'IPROPOSEDEXAMINATIONALTERNATIVENMPCintendstoinspecttheRPVaxialshellweldsusingpersonnelandproceduresqualifiedtothePerformanceDemonstrationInitiative,(PDI).TheautomatedultrasonicexaminationswillbeperformedusingtheGeneralElectricRemoteInspectionSystem(GERIS-2000).TheGERIS-2000systemandproceduresweredemonstratedandqualifiedtotheASMESectionXI,1992Editionwiththe1993Addenda,AppendixVill.Theexaminationprocedureusesecho-dynamicmotionandtipdiffractioncharacteristicsofflawsfordetectionandsizinginlieuofASMECodeamplitudebasedtechniques.AllaccessibleweldexaminationvolumeswillbeinterrogatedbythesamestraightandanglebeamsearchunitsrequiredbyASMESectionV,Article4andanadditional70degreerefractedlongitudinalsearchunitwillbeemployedtoensureadequateinvestigationoftheRPVaxialweldcladbasemetalinterfaceAcomparisonbetweentheASMESectionV,Article4ultrasonicmethodsandproceduresdevelopedtosatisfythePDIcanbestbedescribedasacomparisonbetweenaprescriptive,complianceprocedure(ASMESectionV)andademonstrativeresultsdrivenprocedure(PDI).AtypicalASMESectionVprocedurederivesexaminationsensitivitytodetectandsizeflawsbasedontheamplitudeofaknownreflectorinacalibrationstandard.Thismethodprovidesameansforstandardizationduringexaminationandwaseasilyspecifiedinapplicabledocumentscontrollingtheprocess.Thisultrasonicmethodhashowever,sincebeenrecognizedaspotentiallyprovidinginaccurateresultsfortheapplication.ThePDIprocess,ratherthanjustspecifyingthemeansbywhichanexaminationwillbeperformed,specifiestheresultsoftheexamination.Simplystated,agroupofinspectionspecimenscontainingactualcracksandimbeddedflawsareprovidedfordemonstrationofaprocedure.TheseflawsareatypicalofthosethatmaybeencounteredinaninsituinspectionofRPVshellweldsandarecharacteristictotheflawacceptancecriteriacontainedinASMESectionXI,therebyvalidatingtheexaminationthroughperformance.ComplianceprocedureswouldhavegreatdifficultyevendetectingthesetypeofflawsduringaPDIprocesssincethereflectiveamplitudesareveryloworevendiscernible.ThedifferencebeingthePDIprocessrequiresdetectionandmeasurementoftipdiffractedsignalswhereasthecomplianceprocessreliesonlargerspecularreflectors.USNRCRegulatoryGuide1.150,AUltrasonicTestingofReactorVesselwcldsDuringPreserviceandInserviceExaminationewasissuedbythcStaffin1981asameanstoinitiateachangetoultrasonicprocedurestoberesultsbasedversuscompliant.Theregulatoryguidecontainsconceptsforflawdetectionandsizingbutfallsshortinprovidingthemeansbywhichtoperformthcdemonstrations.Assuch,thisallowsfordifferentinterpretationsofthcintendedrequirements.Basedsolelyoncost,itwouldbeprohibitiveforanindividuallicenseetodemonstrateultrasonicexaminationproceduresashasbeendonewiththePDIprocess.Theregulatoryguidedoesnotprovideforthcnumberofflawcdspccimcns,blindtests,ormandateancxpcctedlevelofperformanceasdoesPDI.TheregulatoryguideonlyrequiresanestimateofexpcctcdcapabilityTheuseofPDIqualifiedpersonnelandproceduresresultsinamorescnsitivcexaminationandwillprovideaddedassuranceforfiawdctcctionandsizing,meetingorexceedingthccurrentrequircmcntsofthe1989EditionoftheASMESectionXICodeandUSNRCRegulatoryGuide1.150.TheerrorbandforflawsizinghasbeenestablishedwithinthelimitsofASMESectionXI,AppendixVIII..TheaboveinformationandsupportingtechnicaldocumentationcontainedintheBWRVIP-05rcportandNRCSafetyEvaluationprovidesabasisforexcludingtheperformanceofRPVcircumferentialweldsfromtheaugmentedexaminationrequircmcntsofIOCFR50.55a(g)(ii)(A)(2)andASMESectionXIandthattheRPVaxialweldsbeingvolumetricallyexaminedusingPDIandqualiTiedpersonnelandprocedures.NiagaraMohawkfirmlybelicvcspermanentdeferralforexaminationoftheRPVcircumferentialshellweldsforthelifeoftheoriginaloperatinglicenseisjustifiedandpresentsanacceptablelevelofqualityandsafetytosatisfytherequirementsofIOCFR50.55a(a)(3)(i),IOCFR50.55a(a)(3)(ii)and10CFR50.55a(g)(6)(ii)(A)(5).File:RRISI1.WPDISI1-7ofISI1-8

RVVD000N0I)S0~Vtl0$00CLOSLOVtfill.ILAICC~OoOo0)0$0CIV)CORVVDIOIRVVR.ISI,RVVOINCCV9~IOSQoISO'oOIO'101~ISC'IOIILLaLOOI-.>>'.LIOLOSI001QoC~8tLSIOO'L,SOI0'l1000'LSII0'l1$1SOIL'lRSOIPCL200SIIL'lISO0'lIOL0'OPQ'IOCuNIDIIO'OIPCRLIDIuPIOACIIVIIillltllllltOILIER~OIIISIIOACIIVClull~0luPPINIvll0JgOZ~SZITI~ZI-~ITIm-~~O-ITIIITI00)ITIZC~OITIIllZNOH++CS0ZZITI~(IIL00'CSICIneoIICVLIIue

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2ENTDESystem:Class:ReactorPressureVesselQualityGroupA,ASMECodeClass1ComponentDescription:PressureRetainingWeldsinReactorVesselsMEETREIREESectionXI,TableIWB-2500-1,ExaminationCategoryB-Arequires:B1.21CircumferentialHeadWeldsC'ode'Item'No."ComponentID;:,ExaminationDescriptionAccessiblelengthofallweldsB1.22MeridionalHeadWeldsAccessiblelengthofallweldsB1.40HeadtoFlangeWeldB1.30ShelltoFlangeWeld100%ofweldlength100%ofweldlengthC.ELIEFREETEDReliefisrequestedfromperforming100%volumetricexaminationoftheCodeRequiredVolume(CRV)forthosecomponentsidentified,onTable1attached.D.BAELENMP1,aBWR/2,hasaReactorPressureVesselthatwasdesignedandfabricatedtotherulesofASMESectionsIandVill,includingNuclearCodeCase1270Nand1273N.Earlyvintageplantsofthistypeweredesigned,fabricatedanderectedpriortoexaminationrequirementsofASMESectionXI.Specificultrasonic(UT)examinationcriteriawasnotrequiredbyASMEI,III,orVillforpreserviceinspectionofthevesselandwasnotfactoredinto.plantdesign.TheNMP1ReactorPressureVesseldesignprecludesessentially100%examinationoftheweldlengthsduetothefollowing:ClosureHeadTheClosureHeadDollarPlateWeldRV-WD-002,limitsessentially100%examinationofweldlengthduetothephysicallocationofsix(6)nozzlesandthecloseproximityofasteelplatform.Seeattachedsketch.TheClosureHeadMeridionalWelds(8each)RV-WD-003,004,005,006,007,008,009and010,limitsessentially100%examinationoftheweldlengthduetothephysicallocationofeighteen(18)nozzlesandinsulationlugs.FileRRISI2.WPDISI2-1ofISI2-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2TheClosureHeadtoFlangeWeldRV-WD-001,limitsessentially100%examinationoftheweldlengthduetotheconfigurationoftheweldbeingaonesidedexam.SeeattachedsketchBottomHeadAllBottomHeadcircumferentialweldstwo(2)RV-WD-147,RV-WD-162andBottomHeadMeridionalWeldsfourteen(14)RV-WD-148,149,150,151,152,153,154,155,156,157,158,159,160and161areinaccessibleduetoonehundredtwenty-nine(129)ControlRodDrivenozzlesandsixty-four(64)In-coreFluxNozzles.ReactorVesselShelltoFlangeWeldTheReactorVesselShelltoFlangeWeldRV-WD-099limits100%examinationoftheweldlengthduetoGuideRodslocatedatthe0and180degreepositionandtheMainSteamNozzlePlughoses.Inadditiontotheaboveexternalaccesstothereactorpressurevesselbottomheadweldsisconstrainedduetoinadequateclearancesbetweenthebio-shieldwallandvesselinsulation.RV-WD-099(A),(B),(C)and(D),ReactorPressureVesselShelltoFlangeWeldfromtheflangeside,wasdividedintofour(4),equal90degreesegmentsduringtheFirstInserviceInspectionIntervalandtheremainderoftheweldwasexaminedfromthevesselinsidesurfaceattheendoftheinterval.DuringthepreparationoftheSecondInspectionIntervalthesamedivisionprocesswasincludedintheinspectionplaninordertostayconsistentwiththeFirstInterval.NMP1performedtheshelltoflangeweldinthesamesequenceasconductedinthefirstintervalwiththeexceptionofsegmentD,whichwasperformedfromtheshellside.Withthecompletionofrefuelingoutage15,weldRV-WD-099willhavebeenexaminedtotheextentpractical.CompliancewiththeASMESectionXIexaminationrequirementswouldrequirearedesignoftheReactorPressurevessel,whichwouldprovideanunduehardshiponNMPCwithoutacompensatingincreaseinthequalityandsafetyoftheunit.E.LEVEXAANoalternateexaminationsoftheClosureHeadDollarPlateWeldRV-WD-002.Examinetotheextentpractical.NoalternateexaminationsoftheClosureHeadMeridionalWelds(8each)RV-WD-003,004,005,006,007,008,009and010.Examinetotheextentpractical.NoalternateexaminationsoftheClosureHeadtoFlangeWeldRV-WD-001.Examinetotheextentpractical1/3eachperiod.NoalternateexaminationsoftheBottomHeadcircumferentialweldstwo(2)RV-WD-147,RV-WD-162andBottomHeadMeridionalWeldsfourteen(14)RV-WD-148,149,150,151,152,153,154,155,156,157,158,159,160and161,astheyareinaccessible.FileRRISI2.WPDISI2-2ofISI2-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2NoalternateexaminationsoftheReactorVesselShelltoFlangeWeldRV-WD-099.Examinetotheextentpractical.TheextentofexaminationperformedontheReactorPressureVesselwillassureanacceptablelevelofqualityandsafety.F.ILEEEDLEThirdInserviceInspectionIntervalFileRRISI2.WPDISI2-3ofISI2-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2omponentIDRV-WD-001RV-WD-002RV-WD-004RV-WD-010RV-WD-099RV-WD-147RV-WD-148V-WD-149RV-WD-150RV-WD-151RV-WD-152RV-WD-153RV-WD-154RV-WD-155RV-WD-156V-WD-157ComponentDescriptionHeadtoFlangeWeldClosureHeadDollarPlateCirc.WeldCHMerd.WeldCHMerd.WeldShelltoFlangeWeldBHDollarPlateWeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldEstimated.o/oofCRVAchieved67%68%70'/80o/833%0%00/0%000%0%00/0%0%0DescriptionofLimitationObstructedbytwelvenozzles,eighteeninsulationlugs,threeliftinglugsandtheconfigurationofheadtoflangeweld.Obstructedbysix(6)nozzlesandthecloseproximitySteelPlatform.ObstructedbyNozzleN7CandN7PObstructedbyNozzleN7M,N7NObstructedbyGuideRod,MSNozzlePlughosesInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsFileRRISI2.WPDISI2-4ofISI2-8 0

NINEMlLEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2ornponentIDRV-WD-158RV-WD-159RV-WD-159RV-WD-160RV-WD-161RV-WD-162'ComponentDescriptionBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHMerd.WeldBHCirc.WeldEstimated%ofCRYAchieved0%0%00/00/0%0%DesdriptIonofLimitatIonInaccessibleduetoCRDNozzlesandlnCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsInaccessibleduetoCRDNozzlesandInCoreFluxMonitorsFileRRISI2.WPDISI2-5ofISI2-8 0

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-2T81<T142414~424442Ul2177212~-n2422Td21)4U171411Rd00070401RTIsrA0IIUdI,00:04OaITd'1210)224}aa)Ssa14iaaa02Oa101414222~2024.2442ia405Q4i'~140/$8ij)66'e+eeeee.ee,~'M+OeS9'e.ee.e4'e888P'8089ee'ee.~ceo.e6e9ee,-eeSe486888+86888+0epe80,8844+4'86$i4884~a49~6$.8+4iI4.ONI~RlQ172S29C'3U3~~rIrI2,~r1CVRLR!~~FileRRISI2.WPDlsl2-6OFISI2-8'I~,J\

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-200A144FileRRISI2.WPDISI2-7OFISI2-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-20't,~~~~P<~~M~A(NlA)~I(N7H)~~g&8(N70)(N1U)Kp((H'FK)'.gareWE(N14("'4)(~VS)00'ileRRISI2.WPDISI2-8OFISI2-8

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-3COMPONENDEFCATNSystem:Class:ReactorPressureVesselQualityGroupA,ASMECodeClass1ComponentDescription:FullPenetrationWeldsofNozzlesinVessels-InspectionProgram8B.ESEONEESectionXI,TableIWB-2500-1,ExaminationCategory8-Drequires:;,CodeItem:No...':.!Co'mponentID::::.:':,'Examin'ation'Desciiption.,",",',83.9083.100NozzletoVesselWeldsNozzleInsideRadiusSectionAIINozzles,ExamVolumeperIWB-2500-7AllNozles,ExamvolumeperIWB-2500-7ELEFEUEDReliefisrequestedfromperforming100%volumetricexaminationoftheCodeRequiredVolume(CRV)forthosecomponentsidentifiedinTable1attached.DELNMP1,aBWR/2,hasanReactorPressureVesselthatwasdesignedandfabricatedtotherulesofASMESectionsIandVill,includingNuclearCodeCase1270Nand1273N.Earlyvintageplantsofthistypeweredesigned,fabricatedanderectedpriortoexaminationrequirementsofASMESectionXI.Specificultrasonic(UT)examinationcriteriawasnotrequiredbyASMEI,III,orVillforpreserviceinspectionofthevesselandwasnotfactoredintoplantdesign.TheNMP1ReactorPressureVesseldesignofthenozzlesprecludesessentially100%examinationoftheCoderequiredvolumeduetothefollowingconditions:1.Nozzlelocations(closeproximitytoeachother),doesn'tallowenoughscandistancebetweennozzlestointerrogatetheentireCodeRequiredvolume.Nozzleconfigurationsandshelltapersdonotprovideparallelsurface,thereforeprovidingareasofnonscanning.liftinglugsandinsulationlugslimitthescandistancesrequiredtointerrogateportionsofCodevolume.limitedaccessforexaminationpersonnelbetweenthereactorpressurevesselandthebiologicalshieldlimitsthemaximumsearchunitscanningdistanceforeachnozzle.CompliancewiththeASMESectionXIexaminationrequirementswouldrequirearedesignoftheReactorPressurevessel,whichwouldprovideanunduehardshiponNMPCwithoutacompensatingincreaseinthequalityandsafetyoftheunit.FileRRISI3.WPDISI3-1ofISI3-7

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-3LENVEENoalternateexaminationsproposed.Examineeachnozzletovesselweldandinnerradiussectiontotheextentpractical.TheextentofexaminationperformedontheReactorPressureVesselNozzleswillassureanacceptablelevelofqualityandsafety.LEThirdInserviceInspectionIntervalFileRRISI3.WPDISI3-2ofISI3-7

NINEMlLEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-3omponentID01-WD-00101-WD-001-IR01-WD-03301-WD-033-IR31-WD-02131-WD-021-IR31-WD-03031-WD-030-IR31-WD-05131-WD-051-IR31-WD-0601-WD-060-IR32-WD-00132-WD-001-IR32-WD-04332-WD-043-IR32-WD-04432-WD-044-IR32-WD-08332-WD-083-IR32-WD-08432-WD-084-IR32-WD-12332-WD-123-IR32-WD-12432-WD-124-IR-WD-16532-WD-165-IRComponentDescriptionN3ANozzletoVesselN3ANoz.InnerRadiusN3BNozzletoVesselN3BNoz.InnerRadiusN4BNozzletoVesselN4BNoz.InnerRadiusN4ANozzle-VesselN4ANoz.InnerRadiusN4CNozzletoVesselN4CNoz.InnerRadiusN4DNozzletoVesselN4DNoz.InnerRadiusN1ANozzle-VesselN1ANoz.InnerRadiusN2ANozzletoVesselN2ANoz.InnerRadiusN1BNozzletoVesselN1BNoz.InnerRadiusN2BNozzletoVesselN2BNoz.InnerRadiusN1CNozzletoVesselN1CNoz.InnerRadiusN2CNozzletoVesselN2CNoz.InnerRadiusN1DNozzletoVesselN1DNoz.InnerRadiusN2DNozzletoVesselN2DNoz.InnerRadiusEstimated'/oofCRVAchieved87%5491%80.1%790/78%4742.1%82%8486%85%59%33.8%73%75%82%679'/73%75.4%82%67.8%73%754%82%68%73%754%82%DescriptionofLimitationAdjacentnozzle,Bio-shieldwallAdjacentnozzle,Bio-shieldwallManualAdjacentNozzle,Bio-shieldwallGerisAdjacentnozzle,Bio-shieldwallAdjacentnozzle,Bio-shieldwallAdjacentNozzle,Bio-shieldwallAdjacentNozzle,Bio-shieldwall.AdjacentNozzle,Bio-shieldwall.AdjacentNozzle,Bio-shieldwall.AdjacentNozzle,Bio-shieldwall.Bio-shieldwall.Bio-shieldwall.Lug,AdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldwall.BottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessBio-shieldwall.Bio-shieldwall.BottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessLug,AdjacentNozzle,Bio-shieldWallBottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessBio-shieldWallBio-shieldWallBottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessFileRRISI3.WPDISI3-3ofISI3-7

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-3omponentID32-WD-16632-WD-166-IR32-WD-20932-WD-209-IR39-WD-00139-WD-001-IR39-WD-08939-WD-089-IR40-WD-04040-WD-040-IR40-WD-08140-WD-081-IR4.1-WD-01844.1-WD-018-IRComponentDescriptionN1ENozzletoVesselN1ENoz.InnerRadiusN2ENozzletoVesselN2ENoz.InnerRadiusN5ANozzletoVesselN5ANoz.InnerRadiusN5BNozzletoVesselN5BNoz.InnerRadiusN6ANozzletoVesselN6ANoz.InnerRadiusN6BNozzletoVesselN6BNoz.InnerRadiusN9NozzletoVeIN9Noz.InnerRadiusEstimatedofoofCRVAchieved33.8%73%745%82%65%5552.5%793%65.8%895%57.3%78.146.2/048%DescriptionofLimitationLug,Thermocouple,Bio-shieldwallLug,AdjacentNozzle,Bio-shieldWallBottomHeadTaperofShellThicknessBottomHeadTaperofShellThicknessAdjacentNozzle,Bio-shieldWallLug,AdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallAdjacentNozzle,Bio-shieldWallio-siewaBio-shieldWallFileRRISI3.WPDISI3-4ofISI3-7

COE43EZI00)31IEXT303lle0ZT31141051'llTET06014~'RfFI6e'REFIZg\IREFIMIERIALTSAI05GTLIIHATERIALTSA336VI73IIETOZS31IETRZ031IET05031TC05515I"'NOZZLfN4AN40HiCNiofxAHIO311003031TETOZS3lIETOZI31IETOZ031IET0513116105031IET0603116055HOTf5eIITHISIXTANINGIDENTIFIESCOH%tCNISSLIJECTIOINSERTICEINSPECIITxlExAIRHATIlxiSASREOVIREO01ASIASECTIONxlAIETGEFTHEOIHTHEIAPCINSERrlCEINSPECTIONPROGRAHPLAN.ZITHISORAIRHGISIHIEIOEOfORUSEIHCONJIPTCIIOHNlIH'INEIHSERTICEINSPfCITGHpRGGRAHpLAHTFAT.IIISINIEIETEOToPRGTIOEOTATAGEHEITALREPRESENTAIIOHOFIHEIOENIIFlfOCGPPONENIIEGUIPFEHTlUClISNOT10OfUSEOFORANTOTHERPMPOSE.SECIIONxlCLASSI.NOTE>IRISGRAVINGVASCREAIEOUSINGCOHPUIERAIREOGRAFIINCOOHOIHARErixiuaLCHANGESIUlÃNREFEREHCESTCOPORAT@NOCEZ31~566SECTIONxlOGLAOaRrOlaQQWF'63006C,STLITELOHAPIFTANINGF45103.CSIEEI5AIDZ0XZlOZ~SZ~illZp~+illm~gfllIITlM()IllIllZMO+lcn<K2qm(IFEEOWATERNOZZLEASSEI%LY~~IOH'IIOCHIAUARANONANCPONXRLXTRPGR*TIOHNINEHILfPOINTMTCLEARSTATIONIPRTICIXO~HTOfIAILGRAVINGFfEOvAIERNOZZLEASSEs0LrINSEIITICIHSPECIIONPROGRAH~ISIWZ004

0)CDE31O0)CD32SES88I32ie8sY32sO88S32sEN2i3sOI66IRfF>~~12s'REFI"sSSFssssss//132YO88232sO8s532sO88532sOI2532sOI61s'~Is~3+SSSIERIALs314eSBVIIEREOINCDCLHAIERIALSI~182j/sNOZZLEfYAHIOHl832sO88132K%I~32se88<32seI2432sel6632se88232leBIS32se88532Y012532IOI61skIIESsIlIRISORASslNGIOENIIFlfSCOHSICNISSSAIJECIIOINSERYICEINStECIIONfYAs8HAIIONSASREOVIRfOBYASSfSECIIOHIIASE)OEFIHEOIN1HEINCINSERYICEINSPECIIIRIPROGRAHPLAILREFfRENCESsCOH'R4lslHGCE231~56$~SECIIOHXlBOVSNARYOIAGRASAF63886'C.SH.ISELOHSPORASSISSGF45183CSHEEI2ANO28HOIEsIRISORAsslHGM4SCREAIEOUSINGCOHPUIERAIRE0GRAFIISsGOOHOIHAkESSASASSNEHANGf521IRISORASslNGISIHIftOEOFORUSEINCOQUHCIIOHSSIYHYHEISSSERYICfINSPECIIOHPROGR4HtLAHOSA.Y.IIISINIflOEO10PROYIOEOH.YAGESTURALREPRESEHIAIIOHOFIHEIOENIIFIEOC~NISEOVIPSfNIASOISM)IIOBEUSEOFIFIANrOrsonRPURPOSE.3SSECIIOH11CLASSI.xURMZ+ill2I~lll~nKIllI37C)mITIZC~OITIlll2V)O+++COZS~4l~~XITICIRECIRCUL4TIONOUTLETNOZZLE4SSEIRLY~~sk%ssskkISIAOARAHOHAWStOSSSRLYSRPORAYIOHRISEHILEPOIHISASCLEARSIAIIOHstillIC~HIOfIAILORASSINGRECIRCSAAIIOHOVILEINOE?Lf*INSERYICINSPECIIONPROGRAH~ISI.HOI~881

372Ct)OHATEAIALtSAIOSGILIIHATERIALTSA336NOllLfEXAHIO0)Ct)C)0)Et)RlTDAOI~2TDO)3~~21~'AEFI'IRfflttttIUl7-Jl-~Il0002~2ICO)IIS'2~IICOSI~IIDAA2AlIDA)3~IICO)INOTESIIITHISORAVIICIOENllflfSCDPOtCHTSSIXI)ECI10IHSERTICEINStECIIOHfXWRNATIOHSASREOUINEOdrASIASECTIONXlWDOFFTHEOINTHEtPPCINSEATICEINStECTIONtROGRAHPLWL21THISIXIAVINGISINTEICXOFTXIUSEINCOTLIUtCIIONVITH'IHEINSEATICEINSPECIIOIPROGRAHtL4HOtC,TIIISINTEIDEOIOPROTIOEOK.TACEIERALREPAESENTAIIIXIOFIHEIOENIIFIEOCOttOtAHT/EOUIttfNIWDISNOT10SEIISEOfIXIWITOIHEIIPURPOSE.)tSECTIONXlCLASSI.REFEREHCEStCOTEORAVltCCE231S66SECIIOHXlOOUtOARTOIAGWWF~63666.C,SILITELOtfttORAIrlHGF4SIA)CStfEl2AtD26NOIEtIRISORAVIICHASCAE4IEOUSINGCOHPUIEA41OEOGRAFIINGOOHOTHAXEHAHUALCHANGESIMIRNzZlOzgSZmmzI>+mm-Q~O-zlmIllIITIZ~C'll-ClMpIllmZ0)OHIozMzIllIIAfflSTEAHOUTLET-TUBINENOZZLEASSEMBLY~AltlWHeItATNIAGARAHOHANSPORXRCORPORATIONNINEHllfPOINTM%LEARS141IOHIDIOTICOttOtA'HIOETAILORAHIICSIE4HOUTLETTIXISINEtDllLEASSTINSERTICINSPECTIPIPAOGA4HsaJaa+wtitittscNOtO<<ISI.NOIOA)

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISISDSystem:Class:ReactorPressureVesselQualityGroupA,(ASMECodeClass1)ComponentDescription:PressureRetainingWeldsInReactorVesselSectionXI,TableIWB-2500-1,ExaminationCategoryB-Arequires:.Cocfe,'Itemw,'arts",Examined.-'=',N~';~~~,";;,-..'F-.;--:,.;,'.Ex'am,'Rejilrements",-;>Extent"artd:Frequeiicy;::.B1.12B1.30ReactorVesselLongitudinalShellWeldReactorVesselShelltoFlangeWeldIWB-2500-2IW8-2500-4Includesessentially100%ofweldlengthIncludesessentially100%ofweldlengthPursuanttoIWB-2420(b)IfflawindicationsorrelevantconditionsareevaluatedinaccordancewithIWB-3132.4,andthecomponentqualifiesasacceptableforcontinuedservice,theareacontainingsuchflawindicationsshallbereexaminedduringthenextthreeinspectionperiodslistedintheschedulesoftheinspectionprogramsofIWB-2410.ReliefisrequestedfromparagraphIWB-2420(b),fromperformingreexaminationsoftheflawindicationsduringthenextthreeinspectionperiods.D.DuringtheautomatedultrasonicexaminationsoftheReactorPressureVesselshellwelds,severalsub-surfaceindicationswereobservedthatexceededtheacceptancecriteriaofIWB-3000onweldsRV-WD-099andRV-WD-140;WeldRV-WD-099identifiedsix(6)unacceptableflaws,locatedintheregionoftheweldfusionlinesandwereattributedtolackoffusionandthinfilmslagdepositsleftfromthefabricationprocess.WeldRV-WD-140identifiedtwo(2)unacceptableflaws,locatedintheregionoftheweldfusionlinesandwereattributedtolackoffusionandthinfilmslagdepositsleftfromthefabricationprocess.Reviewoftheconstructionradiographs(RT)providedacorrelationwiththeultrasonicindications.AnanalyticalevaluationwasperformedinaccordancewithIWB-3600andtheweldswerefoundtobeacceptableforcontinuedservice.Theseevaluationstookintoconsiderationflawgrowththatisunlikelytooccurwithfabricationrelatedflaws.Theflawswerefoundtobeacceptableforcontinuedserviceuntiltheintendedendofplantlife.ASMECodeCaseN-526,AlternativeRequirementsforSuccessiveInspectionsofClass1and2Vessels,SectionXI,Division1,(attached),providesanalternatetothereexaminationrequiredbyIWB-2420(b).FileRRISI4.WPDISI4-1ofISI4-4

NINEMILEPOINTUNIT1,,THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-4CompliancewiththeASMESectionXIreexaminationrequirementswouldprovideanunduehardshiponNMPC,withoutacompensatingincreaseinthequalityandsafetyoftheunit.Noalternateexaminationsproposed.ReexaminetheflawsalongwiththeCoderequiredexaminationsforweldsRV-WD-140andRV-WD-099ascurrentlyscheduledintheISIProgram.TheextentofexaminationperformedontheReactorPressureVesselwillassureanacceptablelevelofqualityandsafety.ThirdInserviceInspectionIntervalFileRRISI4.WPDISI4-2ofISI4-4

33CODORVVD.ODDSU<<%1~ssITS'sI<<'10'<<0'L0000VCSSCLCLANGOR,.QoQoORVvDIOIC~ktI0'~@jfTTTTTTTTOol11'I~Cl.SIT0'L.SO<<0'l.ST<<0'LS1I0'lSSSS<<IL'N'F~IOSUICLDIN'FSHtllJOIIIIFACIIVCIUtlDllILIKRIGIOURVVD'101'.,OoIDS0oOo84<<SOoCL8790'lZI8S/10'LIS20'oIIIDIocAcIIVCIlailSHROUDSUPPINIVII0RVVDISD<<000ClIDIO'l00'CSSILIlaoCICVAIILH

Figure1FlawLocationPlots(Typical)inCrossSection,RV-WD-099II)gtlat4M~OIS/OI~XIUz~V)2mmzr->+mm-~~O~mtm0mm2MOWg)OZ2mXItFigure2FlawLocationPlotsinCrossSection,RV-WD-140

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-5System:Class:ReactorPressureVesselQualityGroupA,ASMECodeClass1ComponentDescription:IntegralAttachmentsForClass1Vessels,Piping,PumpsandValvesN-CodeCaseN-509,Table2500-1,ExaminationCategoryB-Krequires:Code:Item,';No.,',;".;Parts",'Examtnedg:;:,'-',,'.,';.~'..:'~.',ExamRequirements;.ExteritandFrequ'encyB10.10ReactorVesselIntegrallyWeldedIWB-2500-13,14Attachmentsand15100%ofrequiredareasofeachweldedattachmentNote:RegulatoryGuide1.147,Revision12,datedMay1999,isacceptabletotheUSNRCprovidedthatinadditiontothoseconditionsspecifiedintheCodeCase:Aminimum10%sampleofintegrallyweldedattachmentsforeachitemineachcodeclassperintervalshouldbeexamined.C.ETEDReliefisrequestedfromperforming100%ofthelengthoftheattachmentweldateachattachmentsubjecttoexamination.D.BLIEFNMP1,aBWR/2,hasanReactorPressureVesselthatwasdesignedandfabricatedtotherulesofASMESectionsIandVill,includingNuclearCodeCase1270Nand1273N.Earlyvintageplantsofthistypeweredesigned,fabricatedanderectedpriortoexaminationrequirementsofASMESectionXI.Ofthe(6)integralattachmentssubjecttoexamination,four(4)aretheearthquakestabilizerbracketsandtwo(2)are.thereactorpressurevesselsupportskirtintegralattachment,whichisbrokendownintoinsidesurfaceandoutsidesurface.EARTHQUAKESTABILIZERBRACKETATTACHMENTSThefour(4)alloysteelReactorVesselearthquakestabilizerattachmentsbracketsarelocatedat22.5,112.5,202.5and292.5degreeaxispointsaroundtheoutercircumferenceofthevesselapproximatelyeleven(11)feetandeight(8)inchesbelowthevesselflange.Seeattacheddrawingforlocations.Accessforexaminationpurposesonlyallowsamaximumof50%oftheattachmentweldlengthtobeexaminedonallfour(4).REACTORVESSELSUPPORTSKIRTTheReactorVesselsupportskirtisdividedwithintheexaminationplanastwo(2)separateitems,thesebeingtheinsidesurfaceoftheattachmentweldandtheoutsidesurfaceoftheattachmentweld.Accesstothesupportskirtislimitedtotheoutsidesurfaceoftheattachmentweldonly.Theinsidesurfaceisinaccessible.FileRRISI5.WPDISI5-1OFISIS-5 Qi NINEMILEPOINTUNIT1,,THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-5EXAMINATIONREQUIREMENTSTheCodeCaserequiresthatasurfaceexaminationbeperformedinaccordancewithFiguresIWB-2500-13andIWB-2500-15.Theearthquakestabilizerbracket(FigureIWB-2500-15)attachmentsrequiretheweldplus0.50"oneachsideoftheweldandessentially100%oftheweldlengthtobeexaminedbythesurface(MagneticParticleorLiquidPenetrantMethod).Thereactorvesselskirtweld(FigureIWB-2500-13)attachmentrequirestheweldplus0.50"oneachsideoftheweldandessentially100%oftheweldlengthtobeexaminedbythesurface(MagneticParticleorLiquidPenetrantMethod).Theuseoftheultrasonicexaminationmethodinlieuofthesurfaceexamisnotappropriateduetotheaccessprovisionwouldbethesameasthatforthesurfaceexamination.Inadditiontheultrasonicexaminationoftheoutsidesurfaceofthevesselskirtfromonesidewouldbeinappropriateduetothedesignandgeometryoftheskirtbeingnonparallelsurfacesontheforgingknuckle.Theadditionalareasachievedwouldbenegligible.The10%samplerequirementsforthesix(6)CodeItemNumberB10.10integralattachmentswouldrequireasaminimumone(1)integralattachmentrequiredtobeexaminedovertheinterval.CompliancewiththeASMECodeCaseexaminationrequirementswouldrequirearedesignoftheReactorPressurevesselintegralattachments,whichwouldprovideanunduehardshiponNMPCwithoutacompensatingincreaseinthequalityandsafetyoftheunit.NMPCproposestoperformthefollowingexaminations:ScheduletwoofthefourEarthquakestabilizerbracketsforsurfaceexaminationtotheextentpractical.TheanticipatedCodeRequiredAreatobeachievedwillbe50%oneachintegralattachment,whichwouldbeequivalentofcompletingessentiallyonebracket.Inadditiontothestabilizerattachment,NMPCproposestoperformtotheextentpracticalasurfaceexaminationontheoutsidesurfaceoftheRPVSupportskirtonly.TheextentofexaminationperformedontheReactorPressureVesselIntegralAttachmentwillassureanacceptablelevelofqualityandsafety.ThirdInserviceInspectlbnIntervalFileRRISI5.WPDISI5-2OFISI5-5

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-5Componentfde'ntiffcaRV-SB1-IA-371/372RV-SB2-IA-373/374RV-SB3-IA-375/376RV-SB4-IA-377/378RV-WD-356-IDRV-WD-356-OD);Comp'onentDescripttonEarthQuakeStabilizerIntegralAttachmentEarthQuakeStabilizerIntegralAttachmentEarthQuakeStabilizerIntegralAttachmentEarthQuakeStabilizerIntegralAttachmentSupportSkirtIntegralAttachmentSupportSkirtIntegral

Attachment:

.Pe'rcent;(%);of.'RA'to.be,."..'...;;;-achieved:;..'"50%50%50%50%5050%SelectionSelectedSelectedNotSelectedNotSelectedNotSelectedSelectedFileRRISI5.WPDISI5-3OFISI5-5

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTIS[-5FileRRISI5.WPDISI5-4OFISI5-5

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-5/p~]~Pg@Wc~o~SCAN0TluteDg.vII/64Ck'CQubKUdÃm>f~18/I/@lÃ~z%>iWu~055FileRRISIS.WPDISI5-5OFISI5-5

NINEMILEPOINTUNITITHIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-6System:Class:ReactorPressureVesselQualityGroupA,ASMECodeClass1ComponentDescription:PressureRetainingWeldsInControlRodDriveHousingSectionXI,TableIWB-2500-1,ExaminationCategoryB-Orequires:CodeItemPartsExaminedNo,ExamRequirementsExtentandFrequencyB14.10ReactorVesselWeldsinCRDHousingIW8-2500-1810%ofthePeripheralCRDHousingsrequiredPursuantto10CFR50.55a(g)(6)(i)NMPCrequestsrelieffromperforming100%oftheCodeRequiredVolumeof10%oftheperipheralCRDHousingweldslengthasdefinedinFigureIWB-2500-18.BAIRENMP1,aBWR/2,hasanReactorPressureVesselthatwasdesignedandfabricatedtotherulesofASMESectionsIandVill,includingNuclearCodeCase1270Nand1273N.Earlyvintageplantsofthistypeweredesigned,fabricatedanderectedpriortoexaminationrequirementsofASMESectionXI.Thereareonehundredtwenty-nine(129)ControlRodDriveHousingslocatedonthebottomhead.Thirty-two(32)areperipheralCRDHousingforwhich10%or3arerequiredtobeexaminedduringtheinterval.Asectorofapproximately180degreesofeachCRDperipheralhousingcircumferenceisobstructedbytheadjacentCRDhousingsandtheirhydrauliclines.Seeattacheddrawing.NMPCproposestoperformsurfaceexaminationsonsix(6)oftheperipheralcontrolroddrivehousinginlieuofthe3required.Theadrfltional3housingexaminationswillresultinthesameweldlengthbeingexamined,therebymeetingtheintentoftheCoderequirement.ThisapproachwaspreciouslygrantedperUSNRCSafetyEvaluation,TACNo.M83099,datedApril6,1994.TheextentofexaminationperformedontheControlRodDriveHousingswillassureanacceptablelevelofqualityandsafety.F.ETDFileRRISI6.WPDISI6-1ofISI6-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-6'Comp'on'ent';';.=".:,'.:;.IdentificatIo'n::.'."j';=-'-.-'V-CRD-S1RV-CRD-S3RV-CRD-R1RV-CRD-R5RV-CRD-T3RV-CRD-T7RV-CRD-U2RV-CRD-U6~~pporlent'",Desciiption',:";;CRDHousingWeldCRDHousingWeldCRDHousingWeldCRDHousingWeldCRDHousingWeldCRDHousingWeldCRDHousingWeldCRDHousingWeld:Pete'eiit;(%)-of.,';-'-.-';;:CRA'to:be",.'..'--',,'-,'achieved-"",;;-",.,i50%50%5p5p5p50%50%50%'.Sefectiori:';,'."-;",~;:.;;.;:;";.:;;-'.";,,,"'::.'electedSelectedSelectedSelectedSelectedSelectedNotSelectedNotSelectedFileRRISI6.WPDISI6-2ofISI6-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-67Sl+7144144744i12~21242t2424222l'I~1114141104OT044$0177TdAdATAdIUd00:01OIILTdis~'ebsS1telo1Ies020~10s1s~2!2~4041se141eIO4i~I040d88088Pe~eee"ee.ee,~M~Oet4jSB84Oeeeee~@coveee'ee.sp.ieeo.e~~'&4~eeee6~,e-e8se~'eeeee+eeeee+oeoeee,eeee,oeeej,ee.e~~e++~60.+i~0~N4!>iA4>eiA2T2S29CT3V3QuQuanIlFileRRISI6.WPDISI6-3ofISI6-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-7System:Class:ReactorContainmentSprayQualityGroupB,ASMECodeClass2ComponentDescription:PressureRetainingWeldsinPumpsE0MNAONETASMESectionXI,TableIWB-2500-1,ExaminationCategoryC-G,"PressureRetainingWeldsinPumps,ExaminationItemNumberC6.10,"PumpCasingWelds",requiresasurfaceexaminationof100%weldsinallcomponentsineachpipingrunexaminedunderExaminationCategoryC-F.Incaseofmultiplepumpsofsimilardesign,function,andserviceinasystem,theexaminationofonlyonepumpamongeachgroupofmultiplepumpsisrequired.Theexaminationmaybeperformedfromeithertheinsideoroutsidesurfaceofthecomponent.Systemsaffected"--',::,;-":""'i!"=:,'-.,'-.':;-P'ump.,'.Affected:.WeldhAffected,",'::,".Reason:Affected:80.0ReactorContainmentSpray12180'-03-WD-00980-03-WD-01280-03-WD-01480-03-WD-01080-03-WD-011EmbeddedinConcreteEmbeddedinConcreteEmbeddedinConcreteWhendisassembledWhendisassembled81.0ReactorCoreSpray12181-03-WD-00981-03-WD-01281-03-WD-01481-03-WD-01081-03-WD-011EmbeddedinConcreteEmbeddedinConcreteEmbeddedinConcreteWhendisassembledWhendisassembledNMPCrequestrelieffromASMESectionXI,TableIWB-2500-1,ExaminationCategoryC-G,"PressureRetainingWeldsinPumps,ExaminationItemNumberC6.10,"PumpCasingWelds",ofperformingsurfaceexaminationsof100%v0elds,ofonlyonepumpamongeachgroupofmultiplepumpsinasystem.D.BI0ReactorContainmentSprayPumps,FigureISI-PUMP-002(attached),providedatypicaldrawingofthepump80-03,80-04,80-23and80-24.Thisdrawingidentifiessixteen(16)weldsoneachpumpsubjecttoexamination.Ofthe16weldsten(10)aresubjecttoExaminationCategoryC-Gsurfaceexaminations.Oftheten(10)weldssubjecttosurfaceexamination,three(3)areembeddedinconcrete,andtwo(2)canonlybeexaminedwhenthepumpisdisassembled.ReactorCoreSprayPumps,FigureISI-PUMP-003(attached),providedatypicaldrawingofthepump81-03,81-04,81-23and81-24.Thisdrawingidentifiessixteen(16)weldsoneachpumpsubjecttoexamination.Ofthe16weldsten(10)aresubjecttoExaminationCategoryC-Gsurfaceexaminations.Oftheten(10)weldssubjecttosurfaceexamination,three(3)areembeddedinconcrete,andtwo(2)canonlybeexaminedwhenthepumpFile:RRISI7.WPDISI7-1ofISI7-4

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-7isdisassemblqd.Allthepumpsineachsystemprovidethesamelimitationsaspreviouslydiscussedabove,therefore,thefive(5)weldsinquestionontheselectedpumpcannotbesubstitutedforfive(5)weldsonanotherpump.NMPCconsideredselectinganalternatefive(5)weldsonanotherpumpwithineachsystemtosubstituteforthoseweldsthatareinaccessible.Thisconsiderationwasdismissedastheinformationprovidedwouldnotprovidemeaningfulinformationrelatingtotheinaccessiblewelds.Two(2)ofthefive(5)inaccessibleweldsoneachpumpareaccessiblewhenthepumpisdisassembled,welds80-03-WD-010,011and81-03-WD-010,011.TableIWB-2500-1,footnote(2)allowstheexaminationtobeperformedeitherfromtheinsideoroutsidesurfaceofthepump.Thereforetheseweldswouldberequiredtobeexaminedwhenandifthepumpisdisassembled.Thethree(3)weldoneachpumpthatareembeddedwithinconcreteareinaccessiblefromtheoutsidesurface,butevenifthepumpwasdisassembledwouldprovidesomeaccessibilityproblemsfromtheinsidesurface.NMPCfeelsthattheweldsimbeddedintheconcretewouldprovideangreateracceptablelevelofsafetyoverandabovethelimitedsurfaceexaminationsrequiredbytheExaminationCategoryC-G.NMPCproposestotheextentpractical,andonlywhenthepumpisdisassembledformaintenance,repairandorreplacementtoperformthesurfaceexaminationsonwelds80-WD-03-010,011and81-03-WD-010,011,asrequiredbyExaminationCategoryC-G.Onwelds80-03-WD-009,012,014and81-03-WD-009,012,014,NMPCproposestotheextentpracticalandonlywhendisassembledformaintenance,repairandorreplacementtoperformaVisualexaminationoftheinteriorsurfaceofthepumpcasingembeddedinconcrete.Theexaminationperformedonaccessiblewelds,coupledwiththeproposedexaminationsandthesystempressuretestwillprovideanacceptablelevelofqualityandsafety.F.ThirdInserviceInspectionIntervalG.ACHEDrawingISI-PUMP-003ReactorCoreSprayPumpDrawingDrawingISI-PUMP-002ReactorContainmentSprayPumpDrawingFile:RRISI7.WPDISI7-2ofISI7-4

37330)OCFPPIOPH'N0)EXAHIO80'0)IDMl800)ID.M2M~)~IDM)M.O)NONA800)IDM5MO)IDM6EA)C)0)N.O).ID.OI6N03IDNISUCTION.M~)ID08)N0)ID~l3IMPERCASE~LIAM0)ID.~I'LOIEACASE.LVI0~M.Ol.ID.NIM.03.ID.M2M.03ID~I~N0)"KO~IIM0).IDNTN.O).ID~IS0ISCHAAGEM0)IDONM.0).VO.NS800)ID.M6NO)IDNS800)r0MTN0)ID.NON0)ID809M.0)"ID~OI~N0).ID.~IIM0)ID.~I2M0)IDF13N0)IDOIAM0)ID~ISM03ID~I6fXAHSTTPICALFCXIPH'.O<,M-238N.)iIDIEITHISGRAVINGVASCAEATEOUSINGCDHPUIEAAIDEOGRAFIING00NOIHAKEHANUAI.CHANGESNullNIAGARANOHAVXPORNCOAPOAATNWINOTfSsllTHISGRAVINGIDENTIFlfSC~NTSSUBJECTIOINSERTICEINSPECIIGNEKANINATIDNSASREQUIREDOrASIASECTIOIXlAIDOEFINEOINIHEIOPCINSfrlffINSPECTIOIPLAIL2lTHISGRAVINGISlvlflDEOFORUSEINTHEINSERrICEINSPECIIOIPLANIXX.r.AEFEAENCfSsVTXITHINGIOHI5HI.)Il.ISCIAOGRAVINGrVI<i)I,~DEN.I7)TOSECTIIXIXI,CLASS2SECTTDHXlSQXDARTOTAGIUVLF63812CSNEEI2XEIDNIHVANLNlv)ISOOPIJV'NI~VELDFHPTXIAVINGF~45103CSI8EISl5,15A.I58,15CxxUzg)SZmmzr><m~oK>-mmlmz~C0-OSpmmzM0+MpZz"fllglCl880)ID-OI2~4>>I>>IAN>>N>>4HIICHILfPOINTIDCLE4ASTATIONlHllrf8IICALtut'N)EArlcfIN)PEclIDHPRDGAAHaISIPIAP882

EO3333COOCOH'OEIAHIO4ClCO4I.0).IO~IC4I.0).ID.NTSUCIIOISl~)IONl~I~03IO~IlIIfetERCASELVISlSlIO01~ILOVE4CASE'LIAee41~0)~ID.NTSI.S).IO.4150ISCHARGEe61-03IO.NISl.03.ID.N2SI~Sl.IO.~I~Sl-0)-IDSll6103IO~12410).IONSSl~03IO.NS61~0)IDNC410)IONS~<<II<<APH"61~03SI0)IDNlSl~)IDN24103IDNl6103IONi61.03ION561.0')~IONCSl~03IO.NTSl0)VONS61-0).IO.NSSl0)ID~I~Sl4)ID~IISl0)'IO012Sl0)IOSl)Sl0)'IO'I~610)lD01561~03lOSICEEAHSTIPICALFORtIP41N,Sl236SlNOIfSell'IHISORAIIINGIOEHllfIESCOHVICHISSUS)'ECIIOINSERVlffINSPECTIIXIfEAHIHATIONSASAEIEIIAEOSrASIASECIIONxIIVOOEFIIROINTHEIAPCINSEVICEIeeltECIIGNPLAIL21THISORAVIIDISINIEIOEOFORUSEIHTHEINSERrICEINSPECIIGNPLANOex.r.REFEAEICESe-VORIHINGTI)I15err.)lt<SCIWPI)IAVINGVV.I~r21OEH.12314SECTIOIXI,CLASS2-SECTIOIxlSauoAArDIAGRAMF~C)NT.CSIff1IVEIExxlIHIENLNlV)1546PIPPNIVELDlrveIXVIVIIOf<SIS)CSeffTS13,13A,136.13CIDlfeTHISGRAVINGVASCAEAIEOUSINGCOIWUIERAIOEOORAfIING00NOTHAKEHANUALCHANGESNU~HIAOARAHOHAWEtOWERCOAPORATIOHNINEHILEPOIN'IIAXLEARSTAIR)IIPIITc<<NL<<eeleVERIICALPItPINSEAVICINStfCIIOHtAOGAAH<<ea<<~<<<<eeeere~~<<ISItertN)xUzg)SZ~IllgXIr.<m-g0K~AllC0-mlo2MOWI$0zZ=IzmCDI

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-8B.ArticleIWA-4000ArticleIWA-6000ArticleIWA-7000EIERepairProceduresRecordsandReportsReplacementIWA-4800TherecordsrequiredbyIWA-6000shallbecompletedforallrepairs.IWA-7520(8)CompletedOwner'sReportforRepairsorReplacements,FormNIS-2IWA-6210(c)TheOwnershallprepareinserviceinspectionsummaryreportforClass1and2pressureretainingcomponentsandtheirsupports.IWA-6220(c)InserviceInspectionsummaryreportsshallberequiredatthecompletionofeachinspectionconductedduringarefuelingoutage.Examinations,tests,replacements,andrepairsconductedsincetheprecedingsummaryreportshallbeincluded.IWA-6220(d)Eachsummaryreportshallcontainthefollowing:(2)Owner'sReportforInserviceInspection,FormNIS-1(3)Owner'sReportforRepairorReplacement,FormNIS-2IWA-6230Within90daysofthecompletionoftheInservlceinspectionconductedduringeachrefuelingoutage,theOwnershallfileISISummaryReportswiththeenforcementandregulatoryauthorities.C.RELIEFREQUESTED:Pursuantto10CFR50.55a(a)(3)(i),NMPCrequestsRelieffromthefollowing:1.PreparationoftheOwner'sReportforInserviceInspection,FormNIS-12.PreparationoftheOwner'sReportforRepairorReplacement,FormNIS-23.Submittalofthesummaryreportwithin90daysfollowingcompletionoftheinservlceinspectionconductedduringeachrefuelingoutage.D.BASISFORRELIEF:NMPCfeelsthatthesummaryreportrequiredbyIWA-6000doesnotcontaintheinformationnecessarytoassurecompliancewithCoderequirements,andthereforedoesnotprovideacompensationincreaseinthequalityand/orsafetyatNMP1.ThesummaryreportdoesnotfurnishevidenceofcompliancewiththeASMEBoilerandPressureVesselCode,SectionXI,InspectionProgramB,percentagerequirementsasmandatedbyIWB-2412,IWC-2412,andIWD-2412.Class3componentsareexcludedfromthesummaryreportSubmittal.File:RRISI8.WPDISI8-1ofISI8-6

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-8BothaFinalReportandSummaryReportmustbeprepared,reviewedandapprovedinordertocomplywithSub-articlesIWA-6220andIWA-6310respectively.Thepreparation,review,approvalandcertificationofeachrecordandreport,withinthetimeframeof90daysfollowingcompletionofeachrefuelingoutage,increasessubstantiallythecostsassociatedwithinserviceinspectionactivities,andputsanunreasonabletimeconstraintonNMPCwithoutanincreaseinassuranceofCodecompliance.CodeCaseN-532,"AlternativeRequirementstoRepairandReplacementDocumentationrequirementsandInserviceSummaryReportPreparationandSubmissionasRequiredbyIWA-4000andIWA-6000,SectionXIDivision1",hasnotbeenpublishedinRegulatoryGuide1.147,datedMay1999"InserviceInspectionCodeCaseAcceptabilityASMESectionXI,Division1",however,theUSNRCstaffhasapprovedit'suseatothernuclearstations.TheinformationprovidedinthedocumentationpertainingtotheuseofCodeCaseN-532,canbeusedinthesamemannertoassessthesafetyimplicationsofCodeactivitiesperformedduringtheoutage.AreviewusingtheinformationasprescribedbytheCodeCasewill,therefore,providethesameorimprovedlevelofqualityandsafetyasreviewsthatmaybeconductedusingtheCodereportingrequirements.E.AsanalternatetotherequirementsofIWA-4800,IWA-6000,andIWA-7528(8),NMPCwillimplementASMECodeCaseN-532,"AlternativeRequirementstoRepairandReplacementDocumentationRequirementsandInsetviceSummaryReportPreparationandSubmissionasRequiredbyIWA-4000andIWA-6000',Division1",(Note:1-ASME1992EditionSectionXI).IMPLEMENTATIONSCHEDULE:TheAlternaterequirementsofASMECodeCaseN-532willbeincorporatedintoNMPCInserviceInspectionProgramduringthe3rdTen-YearInterval.G.ATTACHMENTSTOTHERELIEF:ASMECodeCaseN-532,"AlternativeRequirementstoRepairandReplacementDocumentationRequirementsandInserviceSummaryReportPreparationandSubmissionasRequiredbyIWA-4000andIWA-6000,Division1NFile:RRISI8.WPDISI8-2ofISI8-6

CASESOFASMEBOILERANDPRESSUREVESSELCODECASEN-532ApprovalDate:December12,1994SheNumericIndexforexpiretionendenyreeffirmetiondetes.CaseN-532AlternativeRequirementstoRepairandRephcementDocumentationRequirementsandInserviceSummtryReportPreparationandSubmissionasRequiredbyIWA~andIWA~tSectionXI,Division1Inquiry:Whatalternativesmaybeusedtothere-quirementsofIWAA910(d)andIWA-6210(e)forcompletionofFormNIS-2followingrepairorreplace-ment,andIWA-6210(c)and(d),IWA-6220,IWA-6230(b),(c),and(d),andIWA-6240(b)forprep-arationandsubmittalofthcinseivicesumniaryrcportandFortnNIS-1?Reply:ItistheopinionoftheCommitteethatasanalternativetotherequirementsofIWAA910(d),IWA-6210(c),(d),and(c),IWA4220,IWA-6230(b).(c),and(d),andIWA-6240(b),thefollowingprovi-sionsmaybeusecLThisCaseshallbeutilizedatleastuntilthecndoftheinspectionperiodinwhichitwasinvoked.1.0CERTIFICATIONOFTHEREPAIRORREPLACEMENT(o)TheOwner'sRepair/ReplacementProgramshallidentifyuseofthisCase.(b)ARepair/ReplacementPlanshallbepreparedinaccordancewithIWA%140',andshallbcgivenauniqueidentificationnumber.(c)Uponcompletioq~fallrequiredactivitiesassoci-atedwiththeRepair/ReplacementPlan,theOwnershallprepareaREPAIIVREPLACEMENTCERTIFICATIONRECORD,FORMNIS-2A.'llreferencestoIWA~andIWA4000usedinthisCaserefertothel992Edition.(d)FormNIS-2AshallbepresentedtotheInspectorforcertification.(e)ThecompletedFormNIS-2AshallbemaintainedbytheOwner.(0TheOwnershallmaintainanindexofRepair/ReplacementPlansinaccordancewith1WA-6340.Theindexshallidentifytheidentificationnumberrequiredby(b)abovetheinspectionintervalandperiodduringwhicheachrepairorreplacementwascompleted.2.0OWNER'SACTIVITYREPORTPREPARATIONANDSUBMITTALAnOWNER'SACTIVEREPORTFORMOAR-1shallbepreparedandcertifieduponcompletionofeachrefuelingoutage.EachFormOAR-1preparedduringaninspectionperiodshallbesubmittedfollowingtheendoftheinspectionperiod.EachFormOAR-1shallcontainthefollowing:(a)AbstractofapplicableexaminationsandtestswiththeinformafiionandformatofTablel.(b)Alistingofitem(s)withflawsorrelevantcondi-tionsthatrequiredevaluationtodetermineacceptabilityforcontinuedservice,whetherornottheflaworrelevantconditionwasdiscoveredduringascheduledexaminationortest.Melistingshallprovidethcinfor-mationintheformatofTable2.(c)Abstractforrepairs,replacementsandcorrectivemeasuresperformed,whichwererequiredduetoanitemcontainingaflaworrelevantconditionthatexceededIWB-3000,IWC-3000,IWD-3000,IWE-3000,IWF-3000,or.IWI3000acceptancecriteria;eventhoughthediscoveryoftheflaworrelevantconditionthatnecessitatedtherepair,replacementorcorrectivemeasure,maynothaveresultedfromanexaminationortestrequiredbythisDivision.Ifacceptancecriteria,foraparticularitemisnotspecifiedinthisDivision,theprovisionsofIWA-3100(b)shallbeusedtodeterminewhichrepairs,replacements,andconcctivemeasuresarerequiredtobeincludedintheabstract.TheabstractshallprovidetheinformationintheformatofTable3.829

CASE(continued)N-532CASESOFASMEBOILERANDPRESSUREVESSELCODEFOAMNIS-2AREPAIR/REPLACEMENTCERTIFICATIONRECORDOWNER'SCERllRCATEOFCONFORMANCEIcertifythatthePlannumberrepresentbyRepair/ReplacementieooIIorweeonwnrconformstotherequirementsofSectionXI.TypeCodeSymbolStampCertificateofAuthoritationNo.ExpirationDateSignedOwnerorOwed~Oooenee.toroOateCERTIRCATEOFINSERVICEINSPECTIONI,theundersipned.holdlnp~validcommissionissuedbytheNationalBoardofBoilerandPressureVesselInspectorsandtheStateorProvinceof~ndemployedbyofhaveinspectedtheitemsdescribedinRepair/ReplacementPlannum.berduringtheperiodto~ndstatethattothebestofmyknowledgeandbelief,theOwner,hasperformedalltheactivitiesdescribedintheRepair/ReplacementPlaninaccordancewiththerequirementsofSectionXI.BysigninpthiscertificateneithertheInspectornorhisemployermakesanywarranty,expressedorimplied.concerningtheactivitiesdescribedintheRepair/ReplacementPlan.Furthermore,neithertheinspectornorhisemployershallbeliableinanymannerforanypersonalinjuryorpropertydamageorlossofanykindarisingfromorconnectedwiththisinspection.lnooeoror'XrnaervroCommissionsrreoonolsoonLstere.orownoo.endtreoenw~ieDatelhleformlkoot20)msybeobtainedfromtheorderoootAsME,22tawDrive.sox2200,Foirllold,IIJ010072200.830

CASE(continuedjN-532CASESOFASMEBOILERANDPRESSUREVESSELCODEFOAMOAR-1OWNERrSACTIVITYREPORTReportNumberOwner(NerneendAdornedOIOwner)PlantINerneendAddreeeOIAinuUnitNo.'deddeeeelolCurrentinspectionintervalCommercialservicedataRefuelingoutageno.IIN.2nd,snxedr.edrerlCurrentinspectionperiodIla,mrsadlEditionandAddendaofSectionXIapplicablettheinspectinplanDateandrevisionofInspectionplanEditionandAddendaotSectionXIapplicabletorepairsandreplacements,'haneinspectionplanIcertifythatthestatementsmadeInthisOwner's'Raprecorrect.andthattheexaminations,tests,repairs.replacements,evaluations.andcorrectivemeasuresrepresentedbythisreportnhrequirementsotSectionXI.CertificateofAuthorltatlonNo.ed~ExpirationDateSignOwnerorOwnereDataI.theundersigned.holdingavalidcommissionissuedbytheNationalBoardofBoilerandPressureVesselInspectorsaddtheStateorProvinceofandemployedbyofhaveinspactadtheitemsdescribedinthisOwneVsAcdvityReport.duringtheperiodtoandstatethattothebastotmyknowledgesndbelief,theOwnerhaspertormedallactivitiesrepresentedbythisreportlnaccordancewiththerequirementsofSectionXI.BysigningthiscertifioataneithertheInspectornorhisemployermakesanywarranty,expressedorimplied.concerningthaexaminations.tests.repairs.replacements,evaluationsandcorrectivemaauresdescribedibisrepon.Furthermore,neitherthainspectornorhisemployershallbeliableinanymannerforsnypersonalinjuryorpropertydamageoralossofanykindarisingfromtheconnectedwiththisinspection.CommissionsNeeenuaderrxsINKdwerrnee.endtee~nrerruDataThisformIf00127)mevbeobtainedfromtheOrderOeotASME,22LdwDrtvd.Box2200,feirlteld.HJ070072XO.831

CASE(continued)N-532CASESOFASMEBOILERANDPRESSUREVESSELCODETABLE1ABSTRACTOFEXAMINATIONSANDTESTSExaminationCategoryTotalExaminationsRequiredforTheIntervalTotalExaminationsCreditedforThisPeriodTotalExaminationsCredited(%)ForThePeriodTotalExaminationsCredited(%)ToDateforTheIntervalRemarksTABLE2ITEMSWITHFLAWSORRELEVANTCONDITIONS,THATREQUIREDEVALUATIONFORCONTINUEDSERVICEExaminationCategoryItemNumberItemDescriptionFlawCharacterization(IWA-3300)FlaworRelevantConditionFoundDuringScheduledSectionXIExaminationorTest(YesorNo)TABLE3ABSTRACTOFREPAIRS,REPLACEMENTS,ORCORRECTIVEMEASURESREQUIREDFORCONTINUEDSERVICECodeClassRepair,.Replacement,orCorrectiveMeasureItemDescriptionDescriptionofWorkFlaworRelevantConditionFoundDuringScheduledSectionXIExaminationorTest(Yes/No)DateCompletedRepair/ReplacementPlanNumber832

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-9IWF-5000Class:QualityGroupA,BandC,(ASMECodeClass1,2and3)IdentificationofComponents:MechanicalandHydraulicSnubbersSystems:AllB.ASMEBBPVCode,SectionXi,ArticleIWF-50001989EditioninvokesthesnubberexaminationrequirementsofStandardOMa-1988,Part4,Section2.3.2.2whichstatesthat"examinationsshallbeconductedat18-monthintervals"andspecifiesschedulechangesifunacceptablesnubbersarerevealed.Section2.3.2.3ofStandardOMa-1988requiresthatsubsequentexaminationsforanygivenfailuregroupnotbelengthenedmorethanoneincrementatatime.C.ED'eliefisrequestedfromperformanceofvisualinspectionsofsnubbersat18-monthintervals,andtheassociatedschedulechangesifunacceptablesnubbersarerevealed,asrequiredbyIWF-5000whichinvokesStandardOMa-1988Part4,Section2.3.2.2.Relieffromthe"SubsequentExaminationScheduleAdjustment"ofOMa-1988Section2.3.2.3isalsorequested.D.BELIEF:The18-monthsnubbervisualinspectionscheduleasitappearsinStandardOMa-1988,Part4,Section2.3.2.2assumesthatrefuelingintervalswillnotexceed18months,andisbasedonlyonthenumberofunacceptablesnubbersfoundduringthepreviousvisualinspection,irrespectiveofthesizeofthesnubberpopulation.The18-monthinspectionintervalisincompatiblewithcurrentoperatingcyclelengthsof24months.DuetothelargenumberofsnubbersinuseattheNineMilePointplant,theOMascheduleandsnubberselectionmethodisexcessivelyrestrictiveandresourceintensive.Performanceoftheseinspectionsduringpoweroperation,aswouldbenecessaryundertheOMa18-monthinspectioninterval,wouldresultinexpendituresofsignificantresourcesandwouldsubjectplantpersonneltounnecessaryradiologicalexposurewithnocommensurateincreaseinqualityorsafety.AsconcludedbytheUSNRCstaffinGenericLetter90-09,theproposedalternativeinspectionmaintainsthesameconfidencelevelinsnubberoperability.Theproposedalternativeiscompatiblewiththecurrent24-monthoperatingcycleandgenerallywillallowinspectionstobeperformedduringplantoutages,therebyreducingradiologicalexposureofplantpersonnel.RelieffromSection2.3.2.3,"SubsequentExaminationScheduleAdjustment"isalsorequestedsincethescheduleadjustmentspecifiedinthisSectionofthestandardisbasedontheexaminationintervalsofSection2.3.2.2.ofOMa-1988.InadditiontotheASMECode,SectionXIrequirements,ShockSuppressors(Snubbers)surveillancerequirementsareaddressedinPlantTechnicalSpecifications3.6.4/4.6.4.TherequirementsoftheTechnicalSpecificationssnubbervisualinspectionsandtestingprovidesthenecessaryassuranceforsnubberoperabilityandvisualexaminationrequirementstofulfilltheASMECode,SectionXIrequirementswithoutduplicatingtheinspections.TheproposedalternativeinspectionconformswithUSNRCGenericLetter90-09.FILE:RRISI9.WPDISI9-1ofISI9-3

NINEMILEPOINTUNIT1...THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-9ExaminationsofsnubberswillbeperformedatintervalsandsamplingratesinaccordancewiththerequirementsspecifiedinGenericLetter90-09,"AlternativeRequirementsforSnubberInspectionIntervalsandCorrectiveActions",December11,1990.Thisproposedalternativeisbaseduponthenumberofunacceptablesnubbersfoundduringthepreviousinspection,thetotalpopulationorcategorysizeforeachsnubbertype,andthepreviousinterval.Specifically,thevisualinspectionintervalwillbedeterminedbaseduponthefollowingcriteria:PopulationCategoryColumnA'xtendedIntervalColumn8'epeatIntervalColumnC'educeInterval801001502003001225Thenextvisualinspectionintervalforthepopulationofasnubbercategoryshallbedeterminedbaseduponthepreviousinspectionintervalandthenumberofunacceptablesnubbersfoundduringthatintewal.Snubbersmaybecategorized,basedontheiraccessabilityduringpoweroperation,asaccessibleorinaccessible.Thesecategoriesmaybeexaminedseparatelyorjointly.Thisdecisionshallbemadeanddocumentedbeforeanyinspectionandusedasthebasisuponwhichtodeterminethenextinspectionintervalforthatcategory.Interpolationbetweenpopulationorcategorysizesandthenumberofunacceptablesnubbersispermissible.ThenextlowerintegerforthevalueorlimitforColumnsA,8,Cshallbeusedifthatintegerincludesafractionalvalueofunacceptablesnubbersasdeterminedbyinterpolation.IfthenumberofunacceptablesnubbersisequaltoorlessthanthenumberinColumnA,thenextinspectionintervalmaybetwicethepreviousintervalbutnotgreaterthan48months.IfthenumberofunacceptablesnubbersisequaltoorlessthanthenumberinColumn8butgreaterthanthenumberinColumnA,thenextinspectionintervalshallbethesameasthepreviousIntervyl.IfthenumberofunacceptablesnubbersisequaltoorgreaterthanthenumberinColumnC,thenextinspectionintervalshallbetwo-thirdsofthepreviousinterval.However,ifthenumberofunacceptablesnubbersislessthanthenumberinColumnCbutgreaterthanthenumberinColumn8,thenextintervalshallbereducedbyafactorthatisone-thirdoftheratioofthedifferencebetweenthenumberofunacceptablesnubbersfoundduringthepreviousintervalandthenumberinColumn8tothedifferenceinthenumbersinColumns8andC.Thestandard25%extensiononsurveillanceintervalsisapplicabletoanyexaminationintervaldeterminedinaccordancewiththisalternative.Allinserviceinspection(VT-3examinations)ofsnubbersshallbeperformedpertherequirementsoftheNineMilePointUnit1TechnicalSpecifications.FILE:RRISI9.WPDISI9-2ofISI9-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-9F.G.Theproposedalternativeinspectionwillbeimplementedduringthethird10-yearinspectioninterval.NoneFILE:RRISI9.WPDISI9-3ofISI9-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-10DClass:IdentificationofSystem:AllAllB.DEEEArticleIWA-4000weldingandbrazingprocedurequalificationrequirements.(a)AllweldingshallbeperformedinaccordancewithWeldingProceduresSpecificationsthathavebeenqualifiedbytheOwnerorrepairorganizationinaccordancewiththerequirementsofthecodesspecifiedintheRepairPrograminaccordancewithIWA-4120.C.D.Pursuantto10CFR50.55a(a)(3)(ii),NMPCrequestsRelieffromtherequirementsofASMESectionXI,ArticleIWA-4000,IWA-4400.B0ELIE.ThebasisforthisreliefistoimplementASMECodeCaseN-573,whicheliminatestheredundancycurrentlyrequiredbytheCodeforeachorganizationtoindependentlyqualifyallweldingprocedureseventhoughtheyhavemetthequalificationprocessatanotherfacility.CodeCaseN-573recognizesandaddressesthisfactandproposesanalternativewhichmaintainsanacceptablelevelofqualityandsafety.ThefollowingalternativetestingrequirementswillbeimplementedasdefinedbyASMESectionXICodeCaseN-573,TransferofProcedureQualificationRecordsBetweenOwners,SectionXI,Division1.1.NMPCwillperformatechnicalreviewofthesupplyingOwner'sPQR2.ThesupplyingOwnerwillstateinwritingthatthePQRwasperformedunderanacceptableNuclearQualityAssuranceprogramthatmeetsASMESectionXI,IWA-1400andthatitwasperformedinaccordancewithASMESectionIX.NMPCwillgenerateaNMPCWPSusingthevariablesestablishedinthesuppliedPQR(s).NMPCPQR'smaysupplementtheseorotherOwnersuppliedPQR's.V4.TheWPSwillbeapprovedandsignedbyNMPC.5.TheWPSwillbedemonstratedsuccessfullybyNMPCbycompletingawelderperformancequalificationtestusingtheparametersoftheNMPCWPS.6.NMPCwillnottransferthesuppliedPQRtoanyotherOwner.7.NMPCwilldocumenttheuseofthisCodeCaseontheappropriateNIS-2form.File:RRISI10.WPDISI10-1ofISI10-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-10TheAlternaterequirementsofASMECodeCaseN-573willbeincorporatedintotheNMPCInserviceInspectionProgramduringthe3rdTen-YearInterva,oruntilCodeCaseN-573isapprovedforgeneralusebyreferenceinRegulatoryGuide1.147.Afterthattime,NMPCwillfollowtheconditions,ifanyspecifiedintheregulatoryguide.ASMECodeCaseN-573,TransferofProcedureQualificationRecordsBetweenOwners,SectionXI,Division1PressureTestofContainmentPenetrationPiping,SectionXl,Division1.File:RRISI10.WPDISI10-2ofISI10-3

CASEN-573CASESOFASMEBOlLERANDPRESSUREVESSELCODEApprovetDate:March1Z,1997SeeNumericalIndexforexpirationandanyreaffirmatfondates.CaseN-$73TransferofProcedureQuaHficationRecordsBetweenOwnersSectionXI,DivisionIInquirytWhatalternativestotheweldingandbraz-ingprocedurequalificationrequirementsofIWAP000maybeused?Reply:ItistheopinionoftheCommitteethatasanalternativetotheweldingandbrazingprocedurequalificationrequirementsofIWAA000,aprocedurequalificationrecord(PQR)qualifiedbyoneOwnermaybeusedbyanotherOwner.Whenthisalternativeisused,thefollowingrequirementsshallbemet:(a)TheOwnerthatperformedtheprocedurequalifi-cationtestshallcertify,bysigningthePQR,thattestingwasperformedinaccordancewithSectionIX.(b)TheOwnerthatperformedtheprocedurequalifi-cationtestshallcertify,inwriting,thattheprocedurequalificationwasconductedinaccordancewithaQualityAssuranceProgramthatsatisfiestherequirementsofIWA-1400.(c)TheOwneracceptingthecompletedPQRshallacceptresponsibilityforobtaininganyadditionalsup-portinginformationneededforWPSdevelopment.(d)TheOwneracceptingthecompletedPQRshalldocument,oneachresultingWPS,theparametersappli-cableto~elding.EachWPSshallbesupportedbyallnecessaryPQR's.(e)TheOwneracceptingthecompletedPQRshallacceptresponsibilityforthePQR.AcceptanceshallbedocumentedbytheOwner'sapprovalofeachWPSthatreferencesthePQR.gTheOwneracceptingthecompletedPQRshalldemonstratetechnicalcompetenceinapplicationofthereceivedPQRbycompletingaperfonnancequalificationtestusingtheparametersofaresultingWPS.(g)TheOwnermayacceptanduseaPQRonlywhenitisreceiveddirectlyRomtheOwnerthatcertifiedthePQR,(h)UseofthisCaseshallbeshownontheNIS-2formdocumentingweldingorbrazing.1145SUPP.8-NC

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-11System:Class:ComponentDescription:00.0ReactorPressureVesselQualityGroupA(ASMECodeClass1)ReactorPressureVesselClosureHeadNutsASMESectionXI,TableIWB-2500-1,ExaminationCategoryB-J,"PressureRetainingBolting,GreaterThan2InchInDiameter,ExaminationItemNumberB6.10,"ReactorVesselClosureHeadNuts",requires100%surfaceexamination.C.RELPursuantto10CFR50.55a(a)(3)(i),NMPCrequestsrelieffromperforminga100%surface(magneticparticle)examinationofthesixty-four(64)ReactorPressureVesselClosureHeadNutsasrequiredbyTableIWB-2500-1.Duetotheclosureheadnutsdistinctsizeandgeometricconfiguration,surface(magneticparticle)examinationmethodsasrequiredbyIWB-2500-1(89Edition),addedconsiderablecostsassociatedwithremoval,preparation(bothpostandpre-cleaning),andexaminationtimewithlittleornocompensatingincreaseinthequalityandsafetyoftheplant.The1989EditionofSectionXIdoesnotprovideacceptancecriteriaforthemandatedsurfaceexaminationofTableIWB-2500-1.ASMESectionXIsubcommitteerecognizedthisminimalincreaseinqualitybymandatingasurfaceexaminationoveravisualexamination,The1989Addenda,TableIWB-2500-1waschangedbyrequiringaVisual(VT-1)examinationoftheReactorVesselClosureHeadNuts,whichalsoreferencedacceptancecriteriaforVT-1examinationofboltinggreaterthan2inches.Boththevisualandmagneticparticleexaminationaddresstheexaminationonthesurfaceofthecomponent.Theadditionalsubsurfacedepthofthemagneticparticleexaminationover.thevisualexaminationofthesurfacedoesnotprovideasubstantialincreaseinthelevelofqualityandsafety,NMPCproposestoutilizetheVisualVT-1examinationrequirementsandacceptancecriteriaofthe1989AddendaofSectionXIforReactorVesselClosureHeadNuts,inlieuofthesurfaceexaminationrequirementsofthe1989Editionwithnoacceptancecriteria.Theextentofexaminationperformedwillprovideanacceptablelevelofqualityandsafety.IMPLEMENTATIONSCHEDULEThirdInserviceInspectionIntervalFile:RRISI11.WPDISI11-1OFISI11-1

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-12System:Class:VariousAugmentedQualityGroupA,(ASMECodeClass1)ComponentDescription:NonconformingServiceSensitivePipingWelds.B.EUDDNUREG0313,TechnicalReportonMaterialSelectionandProcessingGuidelinesforBWRCoolantPressureBoundaryPiping(Reference11),requiresaugmentedvolumetricandsurfaceexaminationofnonconformingservice-sensitivepipingwelds.EEEReliefisrequestedfromperformingfullvolumetricandsurfaceexaminationofnonconformingservicesensitivepipingwelds.Reliefisrequestedfortwenty-one(21)oftheaugmentedpipingwelds.ELIETheweldslistedontheattachedTablewerenotfullyexaminedbyvolumetricand/orsurfaceexaminationmethodsduringthefirstandsecond10-yearintervalduetolimitationsofdesign,geometry,andmaterialofconstruction.Thedendriticweldstructureofthestainlesssteelmaterialcanresultinbothsoundredirectionandattenuationphenomenawhichlimitultrasonicinterrogation.Thus,suchweldsnecessitateexaminationfrombothsidesinordertobefullyexamined.Inparticular,non-parallelsurfacesandproductformofthematerialandproductformofthematerialofvalvesprecludemeaningfulultrasonicexaminationfromthevalveside.Four(4)stainlesssteelweldscontinuetobelimitedbyconfiguration,two(2)bypermanentattachmenttothepipingandfifteen(15)bycontainmentpenetrations.Thepercentageofweldrequiredarea(WRA)andWeldRequiredVolume(WRV)thatwascompletelyexaminedistabulatedwiththenatureoftheobstructionontheattachedTable.PerNUREG-0313,theCoreSpraySystem(40)pipingisdefinedasnonconformingservicesensitive;theextentandfrequencyofexaminationis100%ofthoseweldseveryoutage.OthersystemweldsthathadbeenselectedforthisaugmentedexaminationprogramwerealsoexaminedeachoutageandthushadbeenmorefrequentlyinspectedthanrequiredbyNUREG-0313.Performultrasonicandsurfaceexaminationstotheextentpractical.PerformaVisual(VT-2)examinationoftheinaccessibleIGSCCCategoryweldseachrefuelingoutageforevidenceofleakageperNMPCsubmittaldatedJuly28,1988andSeptember4,1990commitment.Theexaminationsasproposed,togetherwiththeotherpressuretests(asapplicable)provideanacceptablelevelofassuranceofnonconformingservicesensitivepipingweldintegrity.Filo:RRISI12.WPDISI12-1ofISI12-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-12Pursuantto10CFR50.55a(g)(6)(i),thisrequestforreliefwasgrantedperUSNRCSafetyEvaluation,datedApril6,1994,TACNo.M83099,forthesecondinspectioninterval.ApprovalofthisrequestforreliefforthesecondinspectionintervalalsoincludedasubmittaldatedJuly28,1988andSeptember4,1990,thatcommittedtoperformingavisualexaminationoftheinaccessibleIGSCCCategoryweldseachrefuelingoutageforevidenceofleakage.FIIQ:RRISI12.WPDISI12-2ofISI12-3

NINEMILEPOINTUNIT1THIRDINSERVICEINSPECTIONINTERVALRELIEFREQUESTISI-12OMPONENTIDENTIFICATION40-WD-050.A40-WD-010A40-WD.00540.WD.00640.WD-01140.WD.05137-WD003COMPONENTDESCRIPTIONVALVE40-12TOPIPEVALVE40-02TOPIPEPIPETOELBOWPIPETOPIPEELBOWTOPIPEPIPETOELBOWREDUCERTOFLANGEEXAMINATIONMETHODUT/PTUT/PTUT/PTUT/PTUT/PTUT/PTUT/PTEXTENTEXAMINED0%PWRV58%WRA86%WRV82%WRV31%WRA25%WRV50%0%LIMITATIONINACCESSIBLEINSIDEPENETRATIONX-14INACCESSIBLEINSIDEPENETRATIONX-13APERMANENTHANGEROBSTRUCTIONPERMANENTHANGERINTERFERENCEINACCESSIBLEINSIDEPENETRATIONX-14INACCESSIBLEINSIDEPENETRATIONX-14FITTINGCONFIGURATION39.09R-WD.00139-10R-WD.00139-WD-194VALVE39.05TOPIPEUT/PTVALVE39.09RTOPENETRATIONUT/PTVALVE39-10RTOPENETRATIONUT/PTP0%0%CONFIGURATIONCONFIGURATIONINACCESSIBLEINSIDEPENETRATIONX-SB39.WD-194A39-WD.22639-WD-226A38-WD.007PIPETOPIPEVALVE39-06TOPIPEPIPETOPIPEPIPETOPIPEUT/PTUT/PTUT/PTUT/PTP0%P%0%INACCESSIBLEINSIDEPENETRATIONX-SBCONFIGURATIONINACCESSIBLEINSIDEPENETRATIONX-5AINACCESSIBLEINSIDEPENETRATIONX.838-WD-08738-WD08833.WD01433-WD.03633-WD.03533-WD.015VALVE38-12TOPIPEPIPETOPIPEPIPETOPIPEPIPETOELBOWVALVE33-03TOPIPEVALVE33-04TOPIPEUT/PTUT/PTUT/PTUT/PTUT/PTUT/PT0%P0%P%0%PINACCESSIBLEINSIDEPENETRATIONX-7INACCESSIBLEINSIDEPENETRATIONX-7INACCESSIBLEINSIDEPENETRATIONX-9INACCESSIBLEINSIDEPENETRATIONX-154INACCESSIBLEINSIDEPENETRATIONX-154INACCESSIBLEINSIDEPENETRATIONX.9Filo:RRISI12.WPDISI12-3ofISI12-3